POLITICS-On October 17, 2014, a document was uploaded to the website of the California Department of Toxic Substances Control (DTSC). It went out to people on their distribution list for the Santa Susana Field Laboratory. The notice said:
“DTSC- SSFL Document Upload Notification: FAQ – Was there a meltdown at SSFL? Location: Public Involvement / Fact Sheets.” That Fact Sheet was released on a Friday, but on the following Monday, the link to the document no longer worked. Why was this document taken down?
Was there a meltdown at the SSFL?
Why is the discussion of an incident at the Santa Susana Field Laboratory in 1959 – a remote site at the time – so important today? The answer is that non-profits have been calling this incident a “meltdown” or “partial meltdown” for more than three decades. Some people on social media reference this incident as: “America’s Worst Nuclear Meltdown.” As a result, local residents are lead to believe that they, their children’s, or their friend’s cancers are the result of this event in 1959 or other radioactive accidents and spills at this site.
In December 2013, DTSC held a “Scoping Meeting” for their Draft Programmatic Environmental Impact Report on the Santa Susana Field Laboratory.
The following day, DTSC staff made a presentation on the Santa Susana Field Laboratory to the Woodland Hills Warner Center Neighborhood Council (WHWCNC).
At that meeting of the WHWCNC, a Board member asked the DTSC staff if there was a “meltdown” at the SSFL site. The DTSC staff who were present were not able to give an educated response at that time.
The following April 2014, DTSC held an Open House. WHWCNC President Scott Silverstein cancelled their Board’s regularly scheduled Board meeting, and he invited his Board and the community to attend the DTSC Open House. This is the presentation given by DTSC at their April 2014 Open House in Simi Valley: “Santa Susana Field Laboratory Questions Regarding Potential Off-site Issues April 9, 2014.”
That night, WHWCNC President Silverstein asked DTSC management if there was a “meltdown” at the Santa Susana Field Laboratory. The response to the room from DTSC Management was that the DTSC AREA IV project manager was unable to be present, and the DTSC Manager speaking at this event was again not able to give an educated response to that technical question.
That year, the Woodland Hills Warner Center Neighborhood Council and the Canoga Park Neighborhood Council held a Town Hall on the Santa Susana Field Laboratory in October 2014. DTSC staff, Los Angeles Regional Water Quality Control Board (LARWQCB) staff, Boeing, NASA, and the DOE employees all made presentations to an auditorium with about 300 people in attendance at Canoga Park High School. The presentations for that event can be found in the DTSC document library under Public Involvement and Presentations here.
When the DTSC FACT SHEET on the Sodium Reactor Experiment was released on October 17, 2014, I thought DTSC staff would have this document as a handout for the public at that Town Hall. Why wasn’t this information made available to the community at this public forum when DTSC knew that the residents wanted an answer to this question?
So what does the DTSC FACT SHEET say? Was there a meltdown at the SSFL in 1959? (See the link above)
“DTSC does not believe the term provides a useful description of the events that occurred at SSFL in the summer of 1959. A meltdown is commonly understood to mean a catastrophic failure at a nuclear reactor. The term implies loss of cooling to the reactor core, uncontrolled fission and subsequent melting of a large portion of the nuclear fuel with potential containment failure and large-scale release of radioactive materials to the environment. Meltdown (or partial meltdown) is not typically used to communicate technical or regulatory information. The Nuclear Regulatory Commission uses the term core melt accident to describe “an event or sequence of events that result in the melting of part of the fuel in the reactor core.”
“The Department of Energy (DOE) describes the incident that occurred at the SSFL’s Sodium Reactor Experiment (SRE) during a two-week period in July 1959 as a core damage incident. At that time the SRE, a small federally funded research reactor located in the Simi Hills about 30 miles northwest of downtown Los Angeles, suffered significant fuel damage as a result of overheating in the reactor’s core.”
“Through the years, numerous studies of this event have been conducted. Most can be found online here.” (The link on the original fact sheet has not been updated – the DOE website has had changes since 2014.) “These reflect substantial agreement that relatively non-reactive and short-lived radioactive fission products, the noble gases xenon and krypton, did migrate to the helium gas used to blanket the pool of circulating liquid sodium within the reactor core. Following the incident, between July 20th and September 28th 1959, the helium cover gas, which had been contaminated during the accident, was transferred to shielded holding tanks and periodically vented into the atmosphere when levels of radioactivity were deemed safe according to the regulatory standards of the time.”
“Soon after the 1959 incident, the SRE was repaired and new fuel installed. The SRE continued to operate as a research reactor until 1965. Between 1967 and 1978, all nuclear fuel used during SRE operations was removed for reprocessing at DOE’s Savannah River facility. The reactor vessel and all other contaminated structures and equipment were dismantled and removed for disposal as low-level radioactive waste at a DOE facility in Beatty, Nevada. By 1985 all remaining SRE structures had been decommissioned, decontaminated and released for unrestricted use by DOE. In 1999, the last remaining SRE buildings were demolished.”
In August 2009, the Department of Energy hosted an SRE Workshop. Links to videos from that six-hour meeting can be found here.
In his SRE written summary related to the Sodium Reactor Experiment, Dr. Thomas Cochran of the NRDC states:
“I have been asked to review selected documents related to the partial fuel meltdown.”
“Comparative risks: In assessing the risks and harm from the July 1959 accident, it is worth noting that this reactor is small relative to the power of today’s operational nuclear power reactors. The Three Mile Island Unit 2 (TMI-2), which experienced a partial core meltdown accident beginning March 28, 1979, was rated as 2,568 MWt. Its power was 128 times larger than that of the SRE. The TMI-2 reactor was within a sealed secondary containment structure. The SRE reactor had no such sealed secondary containment.”
To the best of my memory at this SRE Workshop almost a decade ago, Dr. Cochran stated at this event that, in his opinion, the SRE did not cause any harm to the community in 1959, and it did not pose any harm to the community today.
At that SRE Workshop, in the presentation by Dr. Paul Pickard of Sandia Labs, Dr. Pickard explained that any of the radionuclides that were released during the overheating of this reactor would have bound with the sodium coolant to form a salt, or with the uranium fuel which is highly reactive. Dr. Pickard, and the other experts – Dr. Cochran and Dr. Richard Denning of Ohio State University, concluded by the fuel inventory that only about 2 % of the fuel at the SRE would have melted.
In conclusion, why isn’t the lead agency, DTSC releasing their fact sheet or an updated one, so that local residents can be made aware that there was no meltdown at the SRE, and that this accident does not pose a risk to local residents today?
Please ask your elected officials to ask for this fact sheet or a similar document to be released so that people do not live in fear that radiation from this 1959 event can cause harm to the communities in Los Angeles and Ventura Counties.
(Chris Rowe has been a 41-year resident of West Hills, was a former West Hills Neighborhood Council Board Member, and has a B.S. in health education. She can be reached at firstname.lastname@example.org. Photo a gift from the Jim Owens Family. The Sodium Reactor Experiment Complex in the foreground. Circa late-19502 to 1060s.) Prepped for CityWatch by Linda Abrams.


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[en] The irradiated FM(Fission-Molly) target is unloaded from the irradiation hole during normal operation, and then cooled down in the reactor pool for a certain period of time. Therefore, it is necessary to identify the minimum decay time needed to cool down FM target sufficiently by natural convection. In the present work, numerical simulations are performed to predict cooling capability of a FM target cooled by natural convection using commercial computational fluid dynamics (CFD) code, CFX. The present study is carried out using CFD code to investigate cooling capability of a FM target cooled by natural convection. The steady state simulation as well as transient simulation is performed in the present work. Based on the transient simulation (T1), the minimum decay time that the maximum fuel temperature does not reach the design limit temperature (TONB-3 .deg. C) is around 15.60 seconds
[en] The Emergency Operating Guidelines (EOG) should be presented to provide technical information to prepare reactor-specific Emergency Operating Procedures (EOP) which cover operation during emergency events. Applicants for operating license and licensees of reactors under construction are required to: - Perform analyses of transients and accidents including multiple failures - Prepare emergency operating guidelines - Upgrade emergency procedures, including procedures for operating with natural circulation conditions - Conduct operator retraining The Procedure Generation Package (PGP) should be submitted to the regulatory body in Korea for the reactor licensing at the same time with Final Safety Analysis Report (FSAR), where PGP includes: - Reactor-Specific Technical Guidelines (RSTGs), - EOP Training Program - EOP Implementation Program The information should comply with those requirements associated with the development of EOG according to the Korean atomic law. All assumptions made in the EOP, which relate to safety analysis, must be verified to be true and appropriate for each user by each user. Furthermore, a set of EOP are required as one of operating procedures that shall be developed for all safety related operations that may be conducted over the lifetime of the facility in research reactors by international standards, Safety of Research Reactors (IAEA NS-R-4) : 7.51 (g) the reactor operator's response to anticipated operational occurrences and DBAs and, to the extent feasible, to BDBAs. In Korea, the regulation on codes and standards for nuclear facilities such as research reactors recommends the nuclear facilities operating organization to prepare EOP. Hence a set of EOG is proposed for helping to develop the EOP in a simplified manner for a research reactor. In this paper, it is described about a development and a revision of a set of EOG for a research reactor
[en] The final phase of commissioning is reactor performance test, which is to prove the integrated performance and safety of the research reactor at full power with fuel loaded such as neutron power calibration, Control Absorber Rod/Second Shutdown Rod drop time, InC function test, Criticality, Rod worth, Core heat removal with natural mechanism, and so forth. The last test will be safety-related one to assure the result of the safety analysis of the research reactor is marginal enough to be sure about the nuclear safety by showing the reactor satisfies the acceptance criteria of the safety functions such as for reactivity control, maintenance of auxiliaries, reactor pool water inventory control, core heat removal, and confinement isolation. After all, the fuel integrity will be ensured by verifying there is no meaningful change in the radiation levels. To confirm the performance of safety equipment, loss of normal electric power (LOEP), possibly categorized as Anticipated Operational Occurrence (AOO), is selected as a key experiment to figure out how safe the research reactor is before turning over the research reactor to the owner. This paper presents a preliminary analysis of the reactor performance test (LOEP) for a research reactor. The results showed how different the transient between conservative estimate and best estimate will look. Preliminary analyses have shown all probable thermal-hydraulic transient behavior of importance as to opening of flap valve, minimum critical heat flux ratio, the change of flow direction, and important values of thermal-hydraulic parameters
[en] Light water is the coolant that is stored in the reactor pool. For both waters, the cooling system for each is absolutely isolated and run independently. The classification is also different: safety system for cooling light water as coolant and non- nuclear safety for cooling heavy water as reflector. There will be, therefore, only negligible effect on the safety from any failures related to the cooling system for heavy water outside the reactor pool. Failures such as pipe ruptures in the heavy water system inside the reactor pool introduce, however, a different issue concerned with power control. Here the issues are presented and it will be shown that the safety of the research reactor is to be assured. A postulated initiating event related to the power control introduced by downgrading of the heavy water, i.e., a reflector was analyzed by simulating the reactor transient with the RELAP code. The result showed that the fuel integrity is assured using the reactor protection system with acceptable margin
[en] During startup operation, control absorber rods are not located in the equal critical position since they can be manually controlled by an operator without position limitation. Therefore, the power peaking factor in this control mode becomes larger due to the skewed power shape, making the accident consequence worse. In research reactor, the reactor protection system (RPS) has linear power trip and power lograte trip for a safe shutdown of reactor in the accident, and the occurrence of those trips depend both on the initial reactor power and the reactivity insertion rate. Therefore, with a series of sensitive analyses, we identified the most severe combination of initial conditions among the various initial reactor powers and reactivity insertion rates. The model reactor in this analysis is a 5MW pooltype research reactor having two different operation modes; a power operation and a training operation.. Since the accident occurs during startup of the reactor, the training mode without a forced convection results in more severe consequences in a view of fuel integrity. Therefore, the inadvertent withdrawal of a control rod during a startup of training operation is analyzed as a limiting case of the accident. Sensitivity tests with combinations of different initial reactor powers and reactivity insertion rates are performed for an inadvertent CAR withdrawal during startup of the training operation
[en] The procedures may also be used as an aid for assessing and documenting the results of tests. The commissioning procedures should include information that specifies several items. Those are mainly (1) all the activities and performance parameters that are to be measured under specified steady state and transient conditions, (2) the requirements on performance, together with clearly stated acceptance criteria. The final phase of stage C commissioning is reactor performance test, which is to prove the integrated performance (neutron power calibration, Control Absorber Rod drop time, I and C functioning, Rod worth, Core heat removal with natural mechanism) and the safety of the research reactor at full power with fuel loaded. Commissioning procedure was developed to show the safety of the research reactor. Both indirect and direct indicators were selected to show that the safety is ensured: 1) indirect parameters which imply success of safety functions: power, flow, opening valves, system response as-designed; 2) direct parameters which shows no failure of safety functions: no meaningful increase in level of neutron in the cooling system. Preliminary analyses have shown all probable thermal-hydraulic transient behavior of importance as to opening of flap valve, minimum critical heat flux ratio, the change of flow direction, and important values of thermal-hydraulic parameters. A preliminary comparison to conservative estimation has shown that the nuclear reactor safety of the research reactor will be assured by verifying that the reactor power and the PCS flow rate are conservative
[en] The fuel test loop of HANARO has been modeled with MARS code to predict the Peak Cladding Temperature (PCT) which is one of the design criteria for the design basis accidents. The PCTs have been calculated in the various operation parameters such as mass flow rate, coolant temperature, system pressure, the thermal power of test fuel, and the valves of safety function. In case of the room 1 LOCA the PCT increases with the increase of the thermal power, the coolant temperature, and the stroke time of the cold leg loop isolation valves as compared with that calculated in the design operation condition. However the effect of the stroke times of the safety injection valves and the depressurization valves on the PCT is negligible
[en] In research reactor, there is a reactor protection system (RPS) to keep the reactor in safe condition. In relation to the RIAs, the RPS has power trip and power lograte trip variables. The results of RIAs are affected by not only the initial reactor power but also the reactivity insertion rate. Therefore, we selected the parameters of the initial reactor power and the reactivity insertion rate for the sensitivity investigation in this study. Especially, a research reactor with a normal power of 5MW was considered. This sensitivity study was carried out by using RELAP5/MOD3.3. The CHFRs and fuel temperatures were investigated in the various initial reactor powers and reactivity insertions by using RELAP5/MOD3.3. In case of the step insertion of 1.5mk reactivity, the larger the initial reactor power is, the smaller the CHFR is. And in case of the constant reactivity insertion rates, there is a different trend with the initial reactor power. In case of the initial power of 100%FP, the minimum CHFR appears at the maximum reactivity insertion rate. On the other hand, in case of the initial power of 1.5%FP, the minimum CHFR is predicted at the minimum reactivity insertion rate
[en] The thermal hydraulic analysis of a research reactor building becomes much more important during longterm cooling stage in loss of normal electric power if the building is designed as containment to fulfill the enhanced regulation requirements of radiological consequence. Since the existing containment analysis computer codes are oriented to the condition and validated for nuclear power plants, it is necessary that a computer code adequate for the research reactors is developed. The purpose of this paper is to identify the thermal hydraulic phenomena during the long-term cooling of a research reactor and to select the appropriate analysis models and to use it as the basic data for the development of a computer code for reactor building and pool cooling analysis. This paper consists of three steps, and a description of each step is as follows: - PIRT for identification of thermal-hydrodynamic phenomena during long-term cooling of research reactors - Literature review and selection of analysis models for the thermal hydraulic phenomena determined by PIRT - Development of the code structure and algorithm of a computer code for cooling analysis of reactor buildings and pool.
[en] Highlights: • BEPU analysis were performed with a scenario of PCS pumps fail simultaneously. • The results from BEPU and conservative analysis were compared. • The comparing result shows the applicability and advantages of a BEPU safety analysis. - Abstract: Best estimate plus uncertainty (BEPU) is a promising approach to the safety analysis of nuclear reactors, and the uncertainty calculation is a very important concern about it. BEPU ensures realistic safety margins and secures higher reactor effectiveness by adopting best-estimate codes and realistic input data with uncertainties, whereas the previous conservative analysis generates excessive conservatism by considering each input parameter separately. A loss of flow accident (LOFA) of a 5 MW open-pool type research reactor was selected as a sample problem for a BEPU uncertainty assessment. We selected the failures of all primary cooling system (PCS) pumps, which would cause the abrupt reduction of flow and the reversal of core flow. The significant contributors to the reactor safety were identified and then input sets were sampled. For the uncertainty evaluation, 124 calculations were performed. This is the number of code runs required for a 95%/95% level with the 3rd order Wilk’s formula. The MOSAIQUE software developed by Korean Atomic Energy Research Institute (KAERI) was used for automated sampling of the uncertainty parameters, a global uncertainty calculation, and post processing of the results. The critical heat flux ratio (CHFR) and the fuel centerline temperature (FCT) were calculated at the 95%/95% level and were compared with those from conservative analyses. In addition, the impact of each design variables on the safety parameters was estimated by sensitivity analysis.


Russia Warns of Catastrophe if Syria Reactor Hit by US Strike
TEHRAN (Tasnim) - Russia said on Wednesday that a military strike on Syria could have catastrophic effects if a missile hit a small reactor near Damascus that contains radioactive uranium.
The Foreign Ministry called on the UN nuclear agency to urgently assess the risk as the United States considers military action against Syria's government, Reuters reported.
"If a warhead, by design or by chance, were to hit the Miniature Neutron Source Reactor (MNSR) near Damascus, the consequences could be catastrophic," a ministry statement said.
It said that nearby areas could be contaminated by highly enriched uranium and that it would be impossible to account for the nuclear material after such a strike, suggesting it could fall into the hands of people who might use it as a weapon.
Russia urged the International Atomic Energy Agency secretariat to "react swiftly" and present IAEA members "an analysis of the risks linked to possible American strikes on the MNSR and other facilities in Syria".
The IAEA said in a report to member states last week that Syria had declared there was a "small amount of nuclear material" at the MNSR, a type of research reactor usually fuelled by highly enriched uranium.


ISAC and ARIEL
TRIUMF’s rare isotope facilities cover an industrial-scale complex combining two core elements: The existing Isotope Separator and Accelerator (ISAC) facility and the new Advanced Rare Isotope Laboratory (ARIEL). ISAC is further divided into two components, housed in adjacent buildings: ISAC I, for low and medium-energy experiments; and ISAC II for higher-energy experiments.
Each year, over 230 Canadian and international scientists come to TRIUMF to collaborate with our own scientists to carry out forefront experiments using one of almost 20 experimental facilities on topics spanning Nuclear Structure and Dynamics, Nuclear Astrophysics, Electroweak Precision Studies, Materials Science, and Life Sciences.
TRIUMF’s rare isotope facilities are comprised of the following main parts
- Drivers: To create rare isotopes, the 520 MeV cyclotron and the new 30 MeV electron linear accelerator (e-linac) supply high energy protons and electrons respectively to power nuclear reactions in targets.
- Targets and Ion Sources: Targets are materials, for example uranium carbide, that when hit with a driver beam undergo nuclear reactions to produce rare isotopes. A coupled ion source strips an electron from these rare isotopes, ionizing them so that they can be manipulated in an electromagnetic beamline.
- Rare Isotope Beam Delivery Systems:
- Beamlines: Beamlines are specialized conduits for transporting, purifying and bunching rare isotopes from the target to experiments. The beamline includes all the components for preparing the beam, including mass separators, charge breeders and post-target accelerators.
- Mass Separators: From the diverse mix of hundreds of rare isotopes produced in a target, mass separators use the ratio between an ion’s mass and its charge to precisely separate-out the desired rare isotope and create a purified rare isotope beam. From the mass separator the rare isotopes can be delivered to low-energy experiments like TITAN in ISAC-I or accelerated to higher energies.
- Charge Breeders: Rare isotopes must often be further charged to enable their acceleration: the higher the charge, the more efficiently they are accelerated. Charge breeders remove more electrons to create positively charged ions.


The coalition envisions transforming the Midwest into a powerhouse for low-carbon fuel production. It said it will use nuclear power generated by Energy Harbor’s Davis-Besse nuclear station to produce carbon-free hydrogen through electrolysis.
The coalition said the focus on clean hydrogen production through electrolysis avoids the challenge of capturing and sequestering carbon dioxide. Nuclear reactors can produce clean hydrogen by splitting water into hydrogen and oxygen. Methods are being explored to use nuclear energy to produce hydrogen from water by electrolysis, thermochemical, and hybrid processes.
In October 2021, Energy Harbor and the DOE agreed to develop a hydrogen production demonstration project at Davis-Besse in collaboration with Idaho National Laboratory (INL), Xcel Energy, and Arizona Public Service. The plant was chosen due to its proximity to key hydrogen consumers in the manufacturing and transportation sectors of the market.
The DOE also announced $20m (€20.01m) in funding to demonstrate technology that will produce clean hydrogen from the three-unit Palo Verde nuclear power station owned and operated by Arizona Public Service Company in Phoenix, Arizona.
Many believe nuclear has the potential to produce hydrogen in a clean and reliable way. Hydrogen is seen as an important path to drive decarbonisation – including in hard-to-abate sectors such as industry. In power generation, hydrogen is one of the leading options for storing renewable energy, and hydrogen can be used in gas turbines to increase power system flexibility.
Demonstration Projects Underway Around World
More than 40 organisations representing industry, government, nonprofit and academia formed the Nuclear Hydrogen Initiative (NHI) to advance nuclear hydrogen. NHI aims to facilitate the development of nuclear hydrogen demonstrations, engage investors and advocate for policies that support nuclear hydrogen deployment.
NHI says hydrogen produced from nuclear energy is “green” or “clean” in the same way as hydrogen produced from renewable energy, because nuclear energy is a zero-carbon source of electricity and heat.
According to the International Energy Agency, annual global dedicated hydrogen production stands at around 70 million tonnes. The US DOE says a single 1,000-MW nuclear reactor could produce more than 200,000 tonnes of hydrogen each year. Ten nuclear reactors could produce about two million tonnes annually or one-fifth of the current hydrogen used in the US.
According to the IEA, around 12 demonstration hydrogen projects with a combined electrolyser capacity of 250 MW are exploring using nuclear power for hydrogen production. These projects are in Canada, China, Russia, the UK and the US, but the IEA said that not all will be realised.
Davis-Besse is a single-unit pressurised water reactor unit in Oak Harbor, Ohio, and is situated on Lake Erie. The 894-MW PWR was supplied by Babcock & Wilcox and began commercial operation in 1978.


Radioactive strontium has been found on the seabed near the crippled Fukushima Daiichi Nuclear Power Plant, Kyodo reported on Tuesday.
Tokyo Electric Power Company said strontium-89 and -90 was discovered in the seabed soil about 3 kilometers off the coast, some 20 kilometers north and south of the nuclear complex.
Between 10 and 44 becquerels per kilogram of strontium-90 were detected, which has a half-life of 29 years.
Shigeharu Kato, a member of the Nuclear Safety Commission, said further examination was needed to determine if or how the substances can accumulate in marine life, the NHK news agency reported.
A 9.0-magnitude quake struck off Japan's northeast coast on March 11, triggering a tsunami and explosions at the Fukushima Nuclear Power Plant, which caused the worst nuclear crisis since Chernobyl in 1986.
According to Japanese scientists, the tsunami triggered by the quake washed over 561 square kilometers in 23 prefectures. Huge waves reached 10 kilometers (6 miles) inland destroying everything on their way.
The disaster destroyed over 151,000 buildings and killed at least 15,000 people, while 9,893 people still remain unaccounted for.
The government has previously said the damage from the disaster could total $184 billion.


SEOUL, South Korea (AP) -- Material that can be used to make nuclear bombs is stored in scores of buildings spread across dozens of countries. If even a fraction of it fell into the hands of terrorists, it could be disastrous.
Nearly 60 world leaders who gathered Tuesday in Seoul for a nuclear security summit agreed to work on securing and accounting for all nuclear material by 2014. But widespread fear lingers about the safety of nuclear material in countries including former Soviet states, Pakistan, North Korea, Iran and India.
While the threat of nuclear terrorism is considered lower now than a decade ago, especially after the death of Osama bin Laden, the nightmare scenario of a terrorist exploding a nuclear bomb in a major city isn't necessarily the far-fetched stuff of movies.
"It would not take much, just a handful or so of these materials, to kill hundreds of thousands of innocent people and that's not an exaggeration, that's the reality that we face," President Barack Obama told world leaders at the meeting, a follow-up to a summit he hosted in Washington in 2010.
Building a nuclear weapon isn't easy, but a bomb similar to the one that obliterated Hiroshima is "very plausibly within the capabilities of a sophisticated terrorist group," according to Matthew Bunn, an associate professor at Harvard University's John F. Kennedy School of Government.
There's an "immense difference between the difficulty of making safe, reliable weapons for use in a missile or combat aircraft and making crude, unsafe, unreliable weapons for delivery by truck," Bunn said.
The Nuclear Threat Initiative, a Washington-based nonproliferation group that tracks the security of world nuclear stockpiles, said in a January report that 32 countries have weapons-usable nuclear materials. Some countries, such as the United States, maintain strict controls already. However others, including Russia and other former Soviet republics, have struggled to secure their stocks, raising fears of "loose nukes" falling into the hands of terrorist groups.
It's unclear how nations will enforce the summit's goal of securing nuclear material by 2014. The International Atomic Energy Agency shares best practices for securing nuclear material, but the U.N. body has no power to enforce its recommendations.
Some countries on the NTI list are a concern because of their government's ties with militant groups or because of corruption among their officials. Others simply don't yet have good safety practices.
Although Pakistan's small stockpiles of nuclear material are heavily guarded, it is believed to be prone to corruption by officials who may have sympathies to hard-line Islamic militants, Bunn said.
Despite New Delhi's insistence that its nuclear materials are secure, the NTI ranked India among the top five nuclear security risks, saying the government needs more transparency, more independence for its nuclear regulator and tighter measures to protect nuclear material in transit.
India's lax security was displayed in at least two incidents in recent years in which radioactive materials - from a hospital and a university laboratory - were discarded and later ended up in a scrap dealer's shop.
Other recent nuclear scares include a suspected attempt by a crime syndicate in the eastern European country of Moldova to sell weapons-grade uranium to buyers in North Africa. Officials in the country told The Associated Press that 1 kilogram (2.2 pounds) of highly enriched uranium remains in criminal hands and is probably in another country.
The investigation provided fresh evidence of a black market in nuclear material probably taken from poorly secured Soviet stockpiles.
Russia has dramatically improved its nuclear security over the last 15 years, Bunn said, but it has the "world's largest stockpiles in the world's largest number of buildings and bunkers" as well as corruption and a weak security culture and regulations.
North Korea and Iran are viewed with worry because of fears of nuclear proliferation.
But Bunn said both are "likely small parts of the nuclear terrorism problem."
"North Korea has only a few bombs' worth of plutonium in a tightly controlled garrison state," he said. "Iran has not begun to produce weapons-usable material."
At least four terror groups, including al-Qaida and Japan's Aum Shinrikyo doomsday cult, have expressed a determination to obtain a nuclear weapon, said Kenneth Luongo, co-chair of the Fissile Materials Working Group, a Washington-based coalition of nuclear security experts.
Nuclear materials stored at research facilities are generally considered less secure than weapons at military installations, Luongo said. Last year's meltdown at Japan's Fukushima nuclear power plant also shows how terrorists could launch a radiation hazard simply by sabotaging a facility's functions.
While some groups could develop crude missiles or other delivery systems, unconventional weapons such as a single briefcase containing plutonium and a detonator may be an even bigger threat, said Chang Soon-heung, a nuclear expert at the Korea Advanced Institute of Science and technology.
Nuclear security experts say greater political commitment is needed to drive efforts to secure radioactive materials and overcome barriers to international cooperation.
While experts praised this week's nuclear summit as a sign of progress, some doubted whether countries would meet the 2014 deadline for securing the world's loose nuclear material, defined generally as completed weapons, bomb material, or the skills to build them.
"There needs to be more political leadership from the top, and countries need to stop talking about what they're doing individually and acknowledge that this is a cross-border international issue," Luongo said.
AP writers Sam Kim in Seoul and Nirmala George in New Delhi contributed to this report.


The U.S. Nuclear Regulatory Commission approved the indirect transfer of MidAmerican Energy Co.`s 25 percent non-operating ownership interest in Quad Cities Nuclear Power Station, Units 1 and 2, as a result of the acquisition of MidAmerican Energy Holdings Co. by an investor group that includes Berkshire Hathaway Inc.; Omaha, Neb., businessman Walter Scott Jr.; and David L. Sokol, MidAmerican`s chairman and chief executive officer. Pending final regulatory approvals, the deal is expected to clos
Trojan Nuclear Power Plant`s decommissioned reactor vessel is positioned for its placement in a burial trench at Hanford Nuclear Reservation in central Washington. Pressure-wrapped in blue plastic, filled with concrete and wrapped in six inches of steel, the 1,000-ton reactor journeyed via barge 270 miles up the Columbia River. Trojan, the largest U.S. commercial reactor ever taken offline, was shut down in 1993, two decades earlier than planned after a series of problems including a faulty safe
UtiliCorp United named Dr. Shirley Ann Jackson, president of the Rensselaer Polytechnic Institute, to its board of directors. A former chairman of the Nuclear Regulatory Commission, Jackson previously taught as a professor of theoretical physics at Rutgers University and worked as a theoretical physicist at the former AT&T Bell Laboratories.
FirstEnergy Corp. named Robert F. Saunders president of its FirstEnergy Nuclear Operating Co. (FENOC) subsidiary and chief nuclear officer. He succeeds John P. Stetz, who will be reassigned within the FENOC organization. Saunders most recently served as vice president, nuclear site operations, Susquehanna Nuclear Site, for PP&L Inc., formerly Pennsylvania Power & Light Co.
The Tennessee Valley Authority (TVA), one of the largest utilities in the United States, has implemented new operations scheduling software for hourly planning. Savings have come from optimizing the schedule to minimize operating costs. Computer simulation has, in a number of cases, encouraged the utility to idle as many as 12 units to achieve significant cost savings while ensuring generation reliability.
Executives should cringe at the thought that electric utilities` year 2000 (Y2K) readiness might be judged by the "prudence" standard previously applied to nuclear power plants and other large construction projects under the regulatory microscope of state public utility commissions. The popular press, utility financial analysts, and legal pundits worry about a possible tidal wave of litigation relating to Y2K disputes. The predicted tidal wave, however, may only amount to a trickle if advocates
Unicom promoted Robert J. Manning to president of competitive operations; Pamela B. Strobel, executive vice president and general counsel; Frank Clark, senior vice president of corporate and governmental affairs; Ruth Ann Gillis, senior vice president of competitive operations; and Dave Helwig senior vice president of nuclear services in the Nuclear Generation Group.


Enabling High Spectral Resolution of Liquid Mixtures in Porous Media by Antidiagonal Projections of Two-Dimensional 1H NMR COSY Spectra.
The noninvasive, in situ chemical identification of liquid mixtures confined in porous materials is experimentally challenging. NMR is chemically resolved and applicable to optically opaque systems but suffers from a significant loss in spectral resolution in the presence of the magnetic field inhomogeneities typical of porous media. In this work, we introduce a method of analysis of conventional two-dimensional (2D) 1H NMR correlation spectroscopy (COSY) spectra based on the extraction of 1D antidiagonal projections, which are free from line-broadening effects and can therefore be used for chemical species identification. Here, we show the application of the technique to the measurement of linear n-alkanes where the cross-to-diagonal peak ratios are shown to follow a power-law curve as a function of the chain length. This calibration enables quantifying mixtures of linear hydrocarbons confined in any porous material independently of temperature or inter-molecular dynamics. Thus, this is a promising tool for quantitative chemical reaction monitoring studies in heterogeneous systems under operando experimental conditions.


Abstract Variation of radon concentration in ground water in the area of Northeastern Hungary was investigated. Specific geological features of this region result in high radon concentration in well waters (between 100 and 350 Bq l −1) and in the air of dwellings (occasionally as high as 10 000 Bq m −3). The observed radon concentrations of well waters show unpredictable variability both in space and time. In adjacent wells, concentration values may change by a factor of 10. In the case of some wells, a variation by a factor of 3–6 (between 20 and 180 Bq l −1) was measured during a year. Measurements were made in order to find correlations between radon concentration in soil air, radon concentration in water and meteorological parameters, i.e. external air pressure, temperature, wind speed and air humidity. A good correlation (with correlation coefficient of k=−0.84) between radon concentration in soil air and air pressure was found.


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April 6th, 2017|0 Comments
ARCHIMEDES III 9103 is designed to measure the radioactivity level in excavation materials of various nature and define their proper destination
The FREE-AND 16 spectrometric station is a robust and handy system designed to perform spectrometric analysis of materials, coming from nuclear power plants decommissioning activities.
ADMOSYS is an automated Segmented Gamma Scanner station designed to measure drums by means of a high efficiency HPGe detector
AURAS 3000 is a highly automated system for measuring a variety of sample sizes and forms (bags, boxes, barrels, B25 containers, etc…)
The portable CARONTE 9400 gamma monitor has been designed to facilitate quick, user-friendly measurement of radioactivity levels for small objects such as tools and boxes
BOX COUNTER is designed to perform fast gamma radiation monitoring of laundry and small objects and compare the results with the release limits
The PIPE SCANNER system is designed to perform a complete and accurate radiometric scan of the internal and external surfaces of a pipe, tube, or similar conduit
ARCHIMEDES II 9102 WiFi is designed to perform fast measurements of the gamma activity of bags containing waste materials
October 23rd, 2017|0 Comments
The GAMON-D is a gamma dose rate monitoring system series designed for ring monitor systems around nuclear facilities and nationwide environmental monitoring networks
September 24th, 2017|0 Comments
PITAGORA 5700 is a modular and flexible environmental monitoring system , consisting of wall mountable equipment, specifically designed to detect area and air radioactivity.
June 15th, 2017|0 Comments
The GAMON-S spectrometer series has been designed for outdoor and indoor online radiation monitoring, for early environmental warning and emergency response.
April 27th, 2017|0 Comments
The MISTRAL XM monitoring system is designed to sample and monitor the activity concentration in the air, in Marinelli geometry.
The ZB-TC module is a ZigBee (WiFi) transceiver that can be used to communicate data from a probe to its reading unit.
The acquisition and control unit SATURN I 5700 RTM-WM is a compact ratemeter, designed for managing and processing signals from the connected area monitoring detector.
April 26th, 2017|0 Comments
The SATURN I 5700 RTM environmental monitoring unit is a compact and modular ratemeter designed to receive, process and visualize the dose measurement provided by one of the several probe available.
The aerial Beta monitor NAUSICAA 5303 2IC is a system designed to measure Beta activity in the air, compensating for the Gamma background.
The DISCOVERY 5302 IC monitoring unit is a modular system for gamma dose measurements, assembled in a highly protected insulated PVC housing.
The CPMON 5303 monitoring system is composed by a network of cabin stations communicating with a central visualization/management station (host PC) through a radio connection.
The BONNER SPHERES SPECTROMETER consists in an array of thermal neutron detectors, each housed in a spherical polyethylene moderator of different dimensions.
SATURN 5702 is a mobile station equipped with two detectors for gamma and neutron ambient dose equivalent, H*(10), rate monitoring
The NAUSICAA 5301 IC environmental monitoring unit is a modular system for gamma dose measurements
SATURN II is a compact ratemeter designed for managing and processing signals from the connected area monitoring detector
5700 sMON is a complete remote software package for real time control, display and management of an entire monitoring network
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The wide range probe MERCURY GMP WR is composed by 2 energy-compensated Geiger-Müller detectors
PIC is a high-precision directional free-air ion chamber, capable of measuring the intensity of a collimated particle beam passing through its entrance and exit windows.
The PNAI detection unit is based on a NaI(Tl) scintillator probe, designed for high sensitivity gamma radiation measurements of air and gas exhausted from controlled zones
GM-1 is a Geiger-Müller gamma radiation detector lodged in aluminum cylinders together with a built-in HV board, providing power supply, and signal processing electronics.
B-RAD is a portable, hand-held radiation survey meter, capable of measuring the photon dose rate in presence of strong electromagnetic fields.
LUPIN 5401 is a modular system for neutron H*(10) measurements, with excellent performance for detection in pulsed neutron fields
High pressure ionization chambers ICP and ICP-T are designed for environmental area monitoring of the gamma dose rate
The WDMS NT-VK system is designed to collect and monitor radioactive wastewaters, which can obtain the free release only after their radioactivity drops under the values allowed by the laws in force.
The LEM system allows to sample the liquid effluents and to perform a gross gamma measurement of the samples in Marinelli geometry.
BONES is a flexible, lightweight, easy to manipulate and heat resistant polymer, containing a variable concentration of natural Boron, up to 25% in weight.
bSCAN is a compact and advanced instrument designed to perform Thin Layer Radio-Chromatography (TLC) so allows the identification of radioactive mixture and compounds
The foot-hand-clothes monitor VITRUVIUS 8220 is an instrument specifically designed for checking gamma contamination on the body
August 21st, 2017|0 Comments
The D-DSA SyS is a compact desktop system integrating 2 Independent 16k Digital MCA and featuring HV/Preamp for up to 2 spectroscopy detectors (HPGe or scintillator)
Hexagon is a compact, stand-alone dual digital 32k MCA with 2 HV & 2 Preamplifier Power Supply
bMCA is a compact, digital MCA, which can perform Pulse Height Analysis and Multi-Channel Scaling of 14-pin standard
bPAD is a microcontroller-based SCA containing a Preamplifier-Amplifier-Discriminator with TTL digital output and HV power supply
TOPAZ-Pico is a compact, stand-alone digital Multi-Channel Analyzer (MCA) which can perform Pulse Height Analysis
Topaz-X is a compact, stand-alone digital MCA able to perform Pulse Height Analysis of the signal produced by high resolution, Peltier-cooled semiconductor detectors, such as Silicon Drift Detectors.
γstream is an active MCA integrated in a 14-pin photomultiplier tube base suited for portable and mobile gamma-ray spectroscopy
July 18th, 2017|0 Comments
SODIGAM is the only software available on the market for high precision analysis of spectra from scintillation detectors which uses physically correct description of background, baseline and peakshapes.
GammaTOUCH application is a Gamma stream control software for Android's smartphones and tablets
bAxil is a new multiplatform software for the x-ray fluorescence spectrum analysis based on AXIL spectrum analysis methods
MC2 Analyzer is a User Friendly Software for Digital Pulse Height Analysis for CAEN Digital MCA and Digitizers
The XR-Spec is a complete package composed by a Silicon Drift Detector, a Multi Channel Analyzer and an analysis software. It is designed for high resolution X-ray spectrometry
RADARM is an automated low-background gamma-ray spectrometry system based on high-purity germanium detector
September 20th, 2017|0 Comments
MONOLITH is a detection unit composed by a Germanium detectors with a Stirling-cycle refrigerator
The gamma–ray Detection Device is based on a HPGe detector with Electric Machine Cooling
April 7th, 2017|0 Comments
The NitroSPEC is the world’s smallest liquid nitrogen cooled Spectrometer which is based on High Purity Germanium (HPGe) semiconductor detectors
Liquid nitrogen cooled portable HPGe detector for Gamma and X-rays spectroscopy where small dimensions are important
Liquid Nitrogen cooled Planar HPGe detector is designed for high resolution Gamma and X ray spectroscopy
Liquid Nitrogen cooled P-type HPGe coaxial detector is designed for high resolution Gamma spectroscopy
Inorganic scintillator detector assemblies for multiple application
The PPM 9300 monitor has been designed and realized to monitor unauthorized radioactive sources transportation or possible contaminations on persons passing through the device.
March 7th, 2017|0 Comments
GALILEO 9900 series automatically monitor the load of vehicles passing through its structure and detect any gamma emitting radionuclide
CM 9700 is a radiation monitoring device designed to automatically control the gamma contamination in materials being transported on conveyors systems
February 20th, 2017|0 Comments
The VeryFuel is an Non Destructive Assay (NDA) tool for verification of modern fresh fuel assemblies with unprecedented speed
February 7th, 2017|0 Comments
GammaFLY is a airborne gamma ray spectrometer system consisting of 16 NaI(Tl) crystals used for radiometric mapping


5 edition of Status and commercial potential of the Barnwell Nuclear Fuel Plant found in the catalog.
Status and commercial potential of the Barnwell Nuclear Fuel Plant
United States. General Accounting Office
|Statement||by the Comptroller General of the United States.|
|The Physical Object|
|Pagination||, vi, , 34 p.|
|Number of Pages||34|
fuel for commercial nuclear plants. Tey currentlyh manage enrichment processes out of the Paducah, Kentucky, plant and perform research and laboratory functions out of the Portsmouth, Ohio plant. DUF. 6 can be stored in three fors –liquid, gaseousm, or solid. At abient temm eratures and pressures p. Georgia Power wants five more years to complete its Plant Vogtle nuclear expansion project and has replaced Fluor Corp. with Bechtel to oversee construction. The utility estimates the cost to Author: Scott Judy.
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In response to a congressional request, GAO examined the status of the Barnwell Nuclear Fuel Plant and its potential for becoming operational as a commercial ll Nuclear Fuel Plant is a partially constructed plant valued at about $ million.
The plant was officially closed on Decem Get this from a library. Status and commercial potential of the Barnwell Nuclear Fuel Plant: report. [United States. General Accounting Office.]. This raised speculation that the Barnwell Nuclear Fuel Plant - a privately owned, partially constructed reprocessing plant - could become operational.
This report examines the status and the commercial potential of the plant. Three overall observations can be drawn from the information presented in the report. Government and industry have committed South Carolina to a central role in nuclear energy development.
Nuclear plants or nuclear-related industries in South Carolina either completed or being developed include: the Allied General nuclear fuel reprocessing plant at Barnwell; the Chem Nuclear low-level waste storage facility in Barnwell; the Westinghouse fuel fabrication plant in.
Allied Corp. together with its partner General Atomic Co. have finally decided to shut down their nuclear fuel reprocessing facility in Barnwell, S.C.
Unless some business group or consortium comes forward to purchase the plant before Octoberit will be closed.
Allied puts the blame for the closing on the decision made by President Carter in April to ban indefinitely any. Appendix F to 10 C.F.R.
Part 50 on siting a fuel reprocessing plant.6 EBRII fuel reprocessing and refabrication operations were suspended. Allied-General Nuclear Services began constructing a large commercial reprocessing plant at Barnwell, SC.
GE halted construction and decided not to pursue an operating license for its. DOWNLOAD gigawatts (GW) Daily U.S. nuclear capacity outage Range Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 0 10 20 30 U.S. Energy Information Administration based on the Nuclear Regulatory Commission's Status and commercial potential of the Barnwell Nuclear Fuel Plant book Reactor Status Report and Forms EIA Annual Status and commercial potential of the Barnwell Nuclear Fuel Plant book Generator Report and Form EIAM Monthly Update to.
The Barnwell Nuclear Fuel Plant (BNFP) was the first large-scale commercial reprocessing facility in the U.S. consisting of: A fuel-receiving and storage station.
A separations facility to chemically process SNF assemblies into liquid uranium, liquid plutonium, and liquid high-level waste (HLW) using advanced PUREX technology. What does BNFP stand for. BNFP stands for Barnwell Nuclear Fuel Plant. Suggest new definition.
This definition appears rarely and is found in the following Acronym Finder categories: Military and Government; Science, medicine, engineering, etc.
BNFP - Barnwell Nuclear Fuel Plant. Looking for abbreviations of BNFP. It is Barnwell Nuclear Fuel Plant. Barnwell Nuclear Fuel Plant listed as BNFP. Barnwell Nuclear Fuel Plant Status and commercial potential of the Barnwell Nuclear Fuel Plant book How is Barnwell Nuclear Fuel Plant abbreviated.
Status and commercial potential of the Barnwell Nuclear Fuel Plant book Barnwell County; Barnwell County, SC; Barnwell County, South Carolina; Barnwell Mountain Recreation Area; Barnwell.
Reprocessing - AGNS • - Allied-General Nuclear Services began constructing commercial reprocessing plant at Barnwell, SC –Capable of tons/yr – acres –~$M spent • President Carter policy change • - Convinced that the project could not proceed on a privateFile Size: 4MB.
plant at Morris, Illinois, was completed inand the Allied-General Nuclear Services plant at Barnwell, South Carolina, was completed in However, neither plant went into commercial service. The year period of nuclear optimism began to wane in about with growing public apprehension over the possibility of a major nuclear accident.
Nuclear Plant Leak in South Carolina West coast cities are not the only ones seeing radiation increase near their water. The South Carolina Department of Health and Environmental Control confirmed a leak from a nuclear power plant has affected drinking water for communities near the Barnwell Nuclear : Alan Reese.
Robert O. Pohl papers, Experimental and Analytical Studies of the Thermal Aspects of Deep Geologic Disposal of Commercial Nuclear Wastes, Technical Report. November Draft Supplement to the Final Environmental Statement related to construction and operation of Barnwell Nuclear Fuel Plant.
June Box The plant makes nuclear fuel assemblies for atomic energy plants around the world. Westinghouse was the chief contractor on the V.C. Summer nuclear construction : Sammy Fretwell.
The Energy Department has already spent about $ billion on the half-built plant near Aiken, S.C., designed to make commercial reactor fuel out of plutonium from nuclear bombs.
Hwy West Fork, AR Phone: () The only US reprocessing facility to ever operate on a commercial basis was the Nuclear Fuel Services (NFS), West Valley, NY Plant. It was permanently shut down in after six years of operation. The initial core from Indian Point 1 was fabricated with HEU/thorium fuel, and it was reprocessed at the NFS Plant in late The Savannah River Site (SRS) is a nuclear reservation in the United States in the state of South Carolina, located on land in Aiken, Allendale, and Barnwell counties adjacent to the Savannah River, 25 miles (40 km) southeast of Augusta, site was built during the s to refine nuclear materials for deployment in nuclear weapons.
It covers square miles (. Nuclear reprocessing is the chemical separation of fission products and unused uranium from spent nuclear fuel. Originally, reprocessing was used solely to extract plutonium for producing nuclear commercialization of nuclear power, the reprocessed plutonium was recycled back into MOX nuclear fuel for thermal reactors.
The reprocessed uranium, also. The commercial LWR power system emerging in the s answered the need for a nuclear fuel cycle that could enable many nations to use nuclear energy peacefully for medicine and power production while and Bechtel designed and built the commercial plant at Barnwell and designed the Exxon plant.
The National Academies Press. doi: That’s why the installation at Plant Hatch, the first of its kind at a commercial nuclear facility, “is not a small step, but a leap for our industry,” said Southern Nuclear’s Nuclear Fuel.
James A FitzPatrick Nuclear Power Plant, Scriba, NY, NYS Power Auth's 1st nuclear plant, goes into commercial operation, 5 yrs after construction started; others operating in state are Con Ed's 2. The initial wave of nuclear power plant construction in the United States, from –was followed by a period of re-evaluation of the economics of nuclear plants, questions on the safety of the entire nuclear fuel cycle, changing requirements for plant operation and staffing, and diverse public discussions of nuclear energy.
The Nuclear Regulatory Commission, which licenses nuclear power plants, lists 63 nuclear reactors in operation - providing per cent of the nation's electricity. Barnwell Complex Update Presented at Governor's Nuclear Advisory Council Meeting Decem Summary. E N E R G Y S O L U T I. N S • Safety • Compliance • Barnwell Disposal Facility (BDF) – New and Used Nuclear Fuel Transport – DOE Classified Shipments.
This plant recycled a substantial quantity of fuel from the Hanford N-Reactor plant. A large plant was built by Allied General Nuclear Services at the Barnwell site in South Carolina, but the plant was never operated for purposes of reprocessing nuclear fuel.
A number of other PUREX plants have operated world-wide, as shown in Table 1. Nuclear Power Plant Accidents and Its Effects By Golam Kibria, Ph.D; April Key points: The potential impact of nuclear power plant accidents could be the release of radioactive materials such as Iodine and Caesium in the Size: KB.
The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption in response to a Marequest from Southern Nuclear Operating Company (SNC or the licensee) in order to use Optimized ZIRLO TM fuel rod cladding material at the Farley Nuclear Plant (FNP), Units 1 and 2, and the Vogtle Electric Generating Plant (VEGP), Units 1 and 2.
Nuclear power plant data as of J Reactor name State Reactor type U.S. Energy Information Administration, Form GC, "Nuclear Fuel Data Survey" (). More spent fuel tables: Table 1. U.S. spent nuclear fuel discharged and stored at commercial sites: Table 3.
Annual commercial spent fuel discharges and burnup, - June Location: Waynesboro, GA (26 miles SE of Augusta, GA) in Region II Operator: Southern Nuclear Operating Co., Inc.
Operating License: Issued - 03/31/ Renewed License: Issued - 06/03/ License Expires - 02/09/ Docket Number: Reactor Type: Pressurized Water Reactor Licensed MWt: 3, Reactor Vendor/Type: Westinghouse Four-Loop.
A portion of the Westinghouse Nuclear Fuel plant has been closed since the buildup was verified in July. The closing resulted in. It is concluded that because Illinois has the largest nuclear power capacity of any state and because it has the oldest privately built commercial nuclear power plant in the country, its state Author: John Glasson.
The spectrum of potential threats of nuclear proliferation is complex and ranges from small terrorist cells to industrialized countries with advanced nuclear. Glossary and a status report for safety standards under development are also available.
For areas of nuclear power, the nuclear fuel cycle, radioactive waste management and decommissioning. LICENSING THE FIRST NUCLEAR POWER PLANT INSAG A report by the International Nuclear Safety Group. North Carolina has nuclear power plants in three counties: Brunswick, Mecklenburg and Wake.
In addition, the mile emergency-planning zone for a South Carolina nuclear plant overlaps into a portion of North Carolina.
All four plants are operated by Duke Energy. The Belene Nuclear Power Plant (Bulgarian: Атомна електроцентрала „Белене“) is a planned nuclear power plant 3 km from Belene and 11 km from Svishtov in Pleven Province, northern Bulgaria, near the Danube was intended to substitute four VVER V reactors of the Kozloduy Nuclear Power Plant that were decommissioned as a prerequisite for Bulgaria to Country: Bulgaria.
The Day - Nuclear plant spent fuel transfer to go on despite coronavirus concerns; KUNM - SAT: New Mexico Land Office Considers Emergency Oil And Gas Rule, + More - By Kunm WBUR - Pilgrim Nuclear Plant Transfer To Go On Despite Coronavirus Concerns - The Associated Press DW - Chernobyl: Radioactive forest near nuclear plant catches fire.
The Institute for 21st Century Energy issued a report that calls on the Obama Administration to commit to a permanent solution for the nation’s used nuclear fuel and nuclear waste.
The report. Victor Dricks Senior Public Affairs Officer Region IV Shortly before 1 p.m. Monday, operators in the control room of the Fort Calhoun nuclear power plant pushed a red button, initiating an automatic shutdown of the reactor.
So ended commercial operations for the nation’s smallest nuclear power plant, located along the Missouri River, about 20 miles. State utility regulator Pdf Tobin is proposing to effectively reduce state renewable-energy rules by counting nuclear energy as a renewable power source to compete with solar and wind.The world’s download pdf commercial nuclear power plant, Calder Hall in Windscale, England, was opened in BBC, " Queen Switches on Nuclear Power".
The first commercial nuclear power plant in America was completed in in Shippingport, Pennsylvania. By the early s, about three dozen small nuclear plants had been built around the world.The nation’s largest electrical grid operator announced Ebook it will examine whether the trend toward more gas-fired power plants and fewer nuclear and coal plants threatens the long-term.


The world’s largest artificial sun, the international thermonuclear experimental reactor (ITER) for the exploration and development of nuclear fusion energy is one of the largest and most far-reaching international scientific projects.
Manufacturing of the core components of the next-generation largest artificial sun, the full-size prototype of the enhanced-heat-flux (EHF) first wall (FW) panel, has been completed in China with its core indexes being significantly better than its design requirements and meeting the conditions for mass manufacturing, marking a new breakthrough by China in the scientific research of the core technology of EHF FW, the Global Times learned from its research team on Tuesday.
Also known as the world’s largest artificial sun, the international thermonuclear experimental reactor (ITER) for the exploration and development of nuclear fusion energy is one of the largest and most far-reaching international scientific projects in the world, and the largest international scientific and technological cooperation project that China participates in as an equal alongside with the EU, India, Japan, South Korea, Russia and the US.
China signed an agreement on the launch of the ITER project with the other six parties in 2006 and has shouldered responsibility for about 9 percent of its tasks.
A new breakthrough was made in research for the “artificial sun” in China in October, with its HL-2M plasma current exceeding 1 million amperes, setting a new record for the operation of controllable nuclear fusion in the country.
The EHF FW panel, which can withstand a surface plasma ion temperature of the reactor core up to 150 million C, some 10 times hotter than the real Sun, during the operation of the ITER, is the most critical core component of the reactor, involving the core technology of the fusion reactor construction.
The technology mastered by China previously took the lead in passing international certification.
The full-size prototype piece of the ITER EHF FW was developed by the Southwestern Institute of Physics under the state-owned China National Nuclear Corp (CNNC).
After the researchers from the institute manufactured EHF FW fingers in batches, they then completed the welding and assembly of the components by overcoming setbacks such as high temperatures, power cuts and COVID-19 outbreaks by cooperating with Guizhou Aerospace Xinli Technology Co, a company specialized in metal smelting and forging, which is located in Zunyi city in Southwest China’s Guizhou Province.
The Chinese team, which took the lead in manufacturing the prototype piece in the international team, once again made a substantial engineering breakthrough for the research and development of the key components of ITER, marking China’s solemn fulfillment of its international commitment.
Luo Delong, director of the China International Nuclear Fusion Energy Program Execution Center under the Ministry of Science and Technology, addressed the achievement and said that great achievements have been made by the Chinese team after years of efforts and lots of fruitful research and development work.
Through the work, China has independently mastered the principle of the process and made breakthroughs in technology while also providing “Chinese wisdom” and “Chinese plans,” making huge contributions to independently master key technologies, fulfilling international commitments and demonstrating its responsibilities as a major power, Luo said.
Originally published at Global Times


Russian prosecutors say a safety breach has caused a radiation leak at a nuclear reprocessing plant in the Ural mountains.
Local officials say a valve believed to be defective allowed radiation to leak from a tank that was holding radioactive liquid waste. The incident occurred on Thursday as the tank was being transported between units of the Mayak plant, near Yekaterinburg.
Prosecutors called the incident a flagrant breach of safety rules in waste transportation.
Officials decontaminated the area and said the radiation is normal inside the plant. No one was injured during the incident.
Russia's Interfax news agency reports Mayak's administration has created a commission to investigate the incident.
Some information for this report was provided by Reuters.


Radiometric dating calculates an age in years for geologic materials by measuring the presence of a short-life radioactive element, e. The term applies to all methods of age determination based on nuclear decay of naturally occurring radioactive isotopes. Bates and Jackson To determine the ages in years of Earth materials and the timing of geologic events such as exhumation and subduction, geologists utilize the process of radiometric decay. Geologists use these dates to further define the boundaries of the geologic periods shown on the geologic time scale. Radiometric decay occurs when the nucleus of a radioactive atom spontaneously transforms into an atomic nucleus of a different, more stable isotope.
Whenever the worldview of evolution is questioned, the topic of carbon dating always comes up. Here is how carbon dating works and the assumptions it is based upon. Radiation from the sun strikes the atmosphere of the earth all day long. This energy converts about 21 pounds of nitrogen into radioactive carbon This radioactive carbon 14 slowly decays back into normal, stable nitrogen. Extensive laboratory testing has shown that about half of the C molecules will decay in 5, years. This is called the half-life.
20.6: The Kinetics of Radioactive Decay and Radiometric Dating
The ease of using the formula for radioactive decay with common elements found in nature make it a powerful tool. Radiometric dating is the technique of using isotopic ratios of common elements to determine the age approximate of materials associated with the element, such as trees, rock strata, fossils, human artifacts and the like. Because radioactive decay follows a specific mathematical formula and is dependent upon unique decay rates half-lives of each element, formulas can be developed that compare the measured amounts of different elemental isotopes. The ratio of the difference is related mathematically to the time that is took for the original sample to decay into the ratios found.
Home earth Earth History Geologist Radioactive. Read about How do we know the Age of the Earth? Radiometric dating using the naturally-occurring radioactive elements is simple in concept even though technically complex. If we know the number of radioactive parent atoms present when a rock formed and the number present now, we can calculate the age of the rock using the decay constant.


Hanford tank farm workers performing routine tasks at the vast nuclear waste site reported getting sick after breathing chemical vapors on Thursday.
The toxic gases most likely escaped from pipes used to move nuclear waste from one area of Hanford to another. Transferring waste always increases the chance of employee exposure to vapors because of the complexity of moving highly radioactive, chemically contaminated nuclear byproducts from aging storage tanks.
Starting around noon, two employees reported a metallic taste in their mouths after removing their personal safety gear. They sought medical attention and the area they were working in, the AP tank farm, was evacuated.
Two hours later two more workers experienced nausea and a dry throat after being exposed to vapors above a line used to transfer waste between the AX and AP tank farms. The area they were working in was evacuated and road blocks were set up as extra precautions. These workers were sent to the onsite medical clinic as well.
Then between 3 pm and 4 pm seven additional workers near a changing trailer outside the AX farm requested medical attention after smelling the strong odor of ammonia.
After the exposures, some employees complained that full respiratory protection wasn’t mandated after the first two workers reported problems mid-day. They also objected to a decision to continue pumping and transferring waste.
Thursday’s vapor exposures are the latest in a series of problematic events at the nuclear site in the last two weeks. On Tuesday, KING 5 broke the story that signs have emerged that a second double-shell tank, AY-101, is beginning to leak.
And last week the KING 5 Investigators found that the leak in AY-102 has greatly expanded since the pumping operation began.
The liquid nuclear waste held in underground tanks is the result of four decades of plutonium production at Hanford for the country’s weapons defense program. Plutonium produced at the site fueled the bomb dropped on Nagasaki in World War II. Production continued through the Cold War to build up the U.S. nuclear arsenal. Since 1989, the only work at Hanford has been related to cleaning up the waste left behind. The most dangerous byproducts are contained in the 56 million gallons of liquid waste housed in the aging underground tanks.
Read more at 11 Hanford workers sick Thurs. from vapors


Most of the reliable reporting about the clean-up of the Fukushima No. 1 nuclear power plant since it suffered three meltdowns in March 2011 has been from on-site workers. Even when articles appear in major media outlets about the situation at the crippled reactor, it's usually presented through the anonymous or pseudonymous firsthand experiences of the men on the front lines.
The site is a nuclear landfill that stored material from Idaho in the 1950s, and also accepted shipments nuclear waste from the Rocky Flats nuclear weapons plant near Denver throughout much of the 1950s and the 1960s. Commercial nuclear waste was also sent to the facility for years, but Idaho officials eventually sued the federal government in an effort to stop the shipments and force the cleanup. The facility currently stores more than 300 metric tons of spent nuclear fuel.
University of Arkansas-Fayetteville official Mike Johnson tells the Arkansas Democrat-Gazette that crews are expected to maintain a "periodic" presence at the shuttered Southwest Experimental Fast Oxide Reactor after April 1. He says there's also a plan allowing for a restart with 45 days' notice to begin removal of the site's radioactive reactor core.


More insight into radioactive salt marshes
- December 16, 2009
- NWO (Netherlands Organization for Scientific Research)
- A researcher has analyzed gamma radiation in salt marshes. The development of salt marshes, vegetated areas periodically flooded by the sea, occurs differently than was previously thought. Knowledge of salt marshes is essential for the development of dynamic but safe coastal zone management.
The development of salt marshes, vegetated areas periodically flooded by the sea, occurs differently than was previously thought. This is apparent from measurements conducted by Dutch researcher Alma de Groot. She analysed the gamma radiation produced by the soil in the salt marsh. Knowledge of salt marshes is essential for the development of dynamic but safe coastal zone management.
Salt marshes, also known as tidal marshes, are coastal areas rich in sediment that are periodically flooded by the sea and where plants have started to grow. Sediments are deposited onto the surface of the marsh by the sea, which gradually raises the bed level. Salt marshes are found on barrier islands, estuaries and sheltered coasts along the North Sea. De Groot studied the salt marshes on the island of Schiermonnikoog. Salt marshes are not only important for biodiversity -- many rare species of plants and birds can be found there -- but also play an important role in coastal defence.
Radioactive salt marshes
The biologist used a novel method for studying the salt marshes: she analysed the gamma radiation naturally present in the sand and the clay of the salt marsh. Most sediments contain small amounts of radioactive elements that emit low levels of gamma radiation. This enabled her to determine the composition of the soil in the salt marshes. She combined the new radiometric method with measurements using a soil corer. She discovered that heavy storms deposit sand on the salt marshes about once every decade, which is far more frequent than was thought until now. The contribution of this sand to the total increase in soil elevation of the salt marsh appears to be small however, meaning that 'normal' sedimentation is by far the most important factor for the growth of the salt marshes.
De Groot's method offers many possibilities for further research. In addition, she shows that commonly used small-scale measurements are insufficient for making reliable predictions about the development of the salt marshes, with respect to rising sea levels for example. This is evident from the complicated sedimentation patterns she discovered in the salt marshes. Her discoveries can be used to improve the set-up of sedimentation measurements.
Dynamic coastal zone management
The possibilities for 'dynamic coastal zone management' are of increasing interest in the Netherlands. Therefore, in certain areas the coast is being left to develop naturally. But this can only be done safely if we understand how our coastline develops. De Groot's research makes a major contribution to such insights.
Alma de Groot's research is part of the NWO programme Land-Ocean Interactions in the Coastal Zone (LOICZ). This programme will be concluded by a symposium on 24 November 2009.
Materials provided by NWO (Netherlands Organization for Scientific Research). Note: Content may be edited for style and length.
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Karl-Heinz Lambertz, the Minister-President of the German-speaking Community of Belgium, paid a working visit to the Belgian Nuclear Research Centre today. The programme included a visit to the underground HADES lab and the BR2 research reactor. Karl-Heinz Lambertz underlined the importance of strengthening and improving nuclear research in Belgium.
The Belgian Nuclear Research Centre invited the German-speaking Minister-President to outline its research activities and future plans. Karl-Heinz Lambertz descended to the HADES laboratory where, at a depth of 225 metres, research is being conducted into the feasibility of storing radioactive waste in layers of clay. SCK•CEN and NIRAS, which are responsible for the management of the nuclear waste, have joined forces for this in the EURIDICE partnership.
Karl-Heinz Lambertz then paid a visit to reactor BR2, one of the most powerful research reactors in the world. SCK•CEN uses the BR2 reactor for materials research and the production of medical radioisotopes for imaging and the diagnosis and treatment of cancer. Silicon is also irradiated in BR2, thus forming a high-grade semiconductor for electronics in high-power applications, such as electric vehicles, wind turbines and solar energy systems.
At the end of the visit the Minister-President underlined the importance of research and innovation and the need for scientifically based information about nuclear technology.
“I am really impressed by the high degree of professionalism. We must improve and strengthen the know-how present in Belgium. In the future there will be many more applications of this technology, which will be of interest both to the field of energy and other fields. Thanks to the Belgian Nuclear Research Centre, we have high-performance research infrastructure to do this”, says Minister-President Lambertz.


Work on the development of nuclear energy in Soviet Russia has begun still in 20-e years of the last century. In the prewar years on the basis of leading scientific institutions of the country program was developed for the implementation of the so-called “uranium project”. But the war brought about changes in the development plans of the industry.
Work in the wartime conditions were not sufficiently intensive. Significant acceleration of them gave a successful test in July 1945 in the U.S. the atomic bomb.
Therefore, the starting point in the history of the domestic nuclear industry is considered to be a 20 August 1945. On this day, Joseph Stalin signed a decree on establishment of the management body of works on uranium – ad hoc Committee under the State Committee of Defense (SCD) of the USSR.
28 September in Russia, in accordance with the presidential decree of 3 June 2005, the Day of nuclear industry worker.
The history of atomic energy of the Russian Federation
On 28 September 1942. was signed a secret order of the State Committee of defense (SCD) of the USSR “About the organization of works on uranium”. The document instructed the Academy of Sciences (an) of the USSR “to resume work on the feasibility study of the use of nuclear energy by fission of uranium and submit by April 1, 1943 report on the possibility of creating a uranium bomb or uranium fuel.”
In 1943, the scientific supervisor of the works on the nuclear issue was appointed Professor LPTI Igor Kurchatov, and under his leadership, the USSR established the Laboratory room 2 (now the national research centre “Kurchatov Institute”).
The decree of GKO of the USSR of 20 August 1945 was formed the Special Committee under the GKO of the USSR, which was responsible for the management of all works on creation of atomic weapons and nuclear industries.
For the creation of the atomic bomb in the Laboratory room 2 Academy of Sciences of the USSR in 1946, was organized by the Design Bureau No. 11 (KB-11; now the Russian Federal nuclear center – all-Russian research Institute of experimental physics, RFNC-VNIIEF; Sarov, Nizhny Novgorod region).
On 29 August 1949 at the Semipalatinsk test site was successfully tested the first Soviet nuclear charge (the product is RDS-1).
In 1951 tested a second atomic bomb, and in 1953 first Soviet thermonuclear bomb (RDS-6s).
Since the late 1940s began the development of the civil sector of the nuclear industry. In 1950 the Council of Ministers of the USSR adopted a resolution “On research, design and experimental works on the use of atomic energy for peaceful purposes”.
In 1953 was formed the Central body of state administration of the USSR on the management of nuclear industry Ministry of medium machine building (Minsredmash; subsequently, the Ministry of atomic energy and industry of the USSR, the Ministry of atomic energy, the Federal atomic energy Agency, 2007 the state Corporation “Rosatom”). On June 27, 1954 in Obninsk, Kaluga region was connected to the mains the world’s first commercial nuclear power plant (now stopped).
Just in the nuclear industry of Russia there are over 400 enterprises and organizations employing more than 240 thousand people. These are enterprises of the nuclear fuel cycle, nuclear energy, scientific research institutes.
Currently in Russia there are 10 nuclear power plants, which are in operation with 28 units. The share in total electricity generation is 17% (in the North-Western regions – up to 37%). Currently the construction of three new nuclear power plants: the Baltic, Leningrad-2 and Novovoronezh-2, as well as additional reactors to existing stations.
Pictures of all 10 Russian NPPs in the gallery.


The PhD work concerns experimental studies of plasma cleaning of so-called first mirrors for future fusion facilities, such as ITER (International Thermonuclear Experimental Reactor). First mirrors will play a crucial role in numerous ITER optical diagnostic systems. Deposition of material eroded from the wall of ITER can degrade the reflectivity of the first mirrors severely. Plasma cleaning using radio-frequency capacitively coupled plasmas is currently being considered as the most promising in-situ cleaning technique. The PhD work will mainly be focused on three different aspects of plasma cleaning for ITER first mirrors:
– Investigation on plasma cleaning in magnetic fields, benchmarked with simulations.
– Development of End of Cleaning Indicator (monitoring of the process).
– Research on driven grounded electrode plasma discharges.


MINSK, 26 June (BelTA) – Belarus is ready to share its experience in implementing the national nuclear energy program with Hungary, Belarus' Energy Minister Viktor Karankevich said as he met with Janos Suli, Hungarian minister responsible for the planning, construction and commissioning of the two new blocks at the Paks Nuclear Power Plant, BelTA learned from the press service of the Belarusian Energy Ministry.
“We are ready to discuss matters related to the construction of the Belarusian nuclear power plant and to share the accumulated experience in implementing the national nuclear energy program,” Viktor Karankevich said.
The parties considered a possibility to establish cooperation in the energy sector, including in nuclear energy.
On the eve of the visit to the Energy Ministry, the Hungarian delegation visited the Belarusian NPP construction site and the town of Ostrovets where they studied Belarus' experience in building infrastructure for construction workers and maintenance personnel of the station. The Hungarian delegation received detailed information about the work of the station's information center, visited a full-scale simulator in a training center and facilities on the NPP's construction site.
“Belarus has enormous experience in creating good living and working conditions for the personnel at such an important facility as the nuclear power plant. Given the comparability of the construction scale, this experience can be used to manage the construction of the two new blocks at the Paks Nuclear Power Plant,” said Janos Suli.
The Belarusian nuclear power plant is being built near Ostrovets, Grodno Oblast using a Russian design featuring two VVER-1200 reactors with the total output capacity of 2,400MW. The first power-generating unit is scheduled for commissioning in 2019, with the second one to go online in 2020.
The interest of the Hungarian specialists in the construction of the Belarusian nuclear power plant is due to the fact that the two new blocks of the Paks Nuclear Power Plant will be built in line with the reference project of Russian NPPs with a VVER-1200 generation 3+ reactor.More about Economy


An International Atomic Energy Agency (IAEA) Integrated Review Service for Radioactive Waste & Spent Fuel Management, Decommissioning & Remediation (ARTEMIS) team said Germany demonstrated commitment to continued development of its national radioactive waste management (RWM) programme since a previous review in 2019. The review team noted that the majority of the initial recommendations and suggestions had been addressed and advised Germany to apply a consistent approach across future activities related to cost assessment of the RWM programme.
The ARTEMIS follow-up mission was carried out at the request of the Federal Ministry for the Environment, Nature Conservation, Nuclear Safety & Consumer Protection (BMUV) to review the implementation of the findings identified during the initial ARTEMIS mission in 2019. It was hosted by Gesellschaft für Anlagen- und Reaktorsicherheit gGmbH (GRS), Germany's central professional organisation in the field of nuclear safety, in the city of Cologne.
The follow-up mission covered all aspects and topics related to the development and implementation of the RWM programme. It focused on the national policy and strategy for the management of radioactive waste, application of selection criteria in the identification of a site for a disposal facility for high level radioactive waste, and cost assessment for the RWM programme. It also reviewed the national plan and cost estimation for the retrieval of waste from the ASSE II former salt mine.
Mission team leader Patrice François, Senior Expert in Radioactive Waste Management & Decommissioning at the Institute for Radiological Protection & Nuclear Safety in France, said: “Germany, as the first country to call for a follow-up ARTEMIS mission, has shown its dedication to meet the findings from 2019 and strong commitment to transparency of communications, in the interest of improving standards of safety in implementing its national programme for radioactive waste management.”
Germany has made the decision to stop generating electricity from nuclear power plants. The three remaining operational NPPs were planned to be shut down by the end of 2022. However, due to the current energy crisis these reactors, with a total net capacity of 4000 MWe, they will remain in operation until 15 April 2023. In view of Germany’s previously large nuclear power programme with a total of 33 reactors, including the three in operation, a significant amount of radioactive waste will be generated by decommissioning activities. The waste will need to be stored until it can be safely disposed.
Currently, Germany does not have a receiving radioactive waste disposal facility. The Morsleben disposal facility has stopped receiving waste and is being closed. A new disposal facility for low and intermediate level waste is being constructed at the site of former iron ore mine Konrad. A nationwide search has begun to identify a site for a disposal facility for high level radioactive waste.
The mission included interviews and discussions with representatives of BMUV, GRS, Federal Office for the Safety of Nuclear Waste Management (BASE), Federal Company for Radioactive Waste Disposal (BGE), Company for Storage (BGZ), as well as a site visit to the Biblis NPP, a pressurised water reactor in permanent shutdown, to observe the status of the dismantling and the management of radioactive waste.
The team found that Germany has successfully implemented many recommended actions from the 2019 mission. Of the three recommendations and 12 suggestions identified in the initial mission, two recommendations and two suggestions require further development, including:
- Updating the cost assessment for the national waste management programme in the Cost Report, based on a consistent approach across all activities, including waste retrieval from Asse II mine.
- Analysing risk and uncertainty when updating the cost assessment for all public sector components of the radioactive waste and spent fuel management programme.
- Assessing whether the geosphere requirements for non-heat generating waste are different from those for high level waste and, if they are, taking them into account in the application of disposal facility siting criteria.
- Making greater use of the radioactive waste inventory to monitor changes in the inventory over time and demonstrate waste minimization.
Gerrit Niehaus, Director General for Nuclear Safety & Radiation Safety at BMUV said: “We are happy that we were able to demonstrate that we made progress, that most of the 2019 findings could be closed and that no new ones were identified. The findings that remain open will be used to guide us on our way to further improve the safe management of radioactive waste in Germany, our national programme and our communication.”
The final mission report will be provided to the Government in about two months.
Image: Drums of radioactive waste stored in the Asse II mine (courtesy of Bilfinger)


In the year of 1953 on March 17, a nuclear bomb test called ANNIE had been done. It was the first nuclear test in Operation Upshot-Knothole where reporters were permitted to see the explosion in first hand.We’ve found a video footage capturing the blast in 1953. And, unlike most videos of the nuclear blasts, this one is raw and edited to the least degree. You are going to see the real blast and hear the real sound.
This footage is really phenomenal. It was shot over a distance of 11 kilometers from the explosion site. And, as per the rules of physics, the sound is heard a few seconds after the blast was seen (light travels faster than sound). The footage resurfaced through an unnamed Russian correspondent and blogger Alex Wellerstein.
Be noted that Annie was a weapon development test. It was shot openly. Civilians were permitted to have the view of the blast from News Nob, which was 11 kilometers away from the south of the shot-tower. “Annie was a weapon development test, it was an experimental device (code named XR3) that provided additional information to normalize the yield-vs-initiation time curve. It was a Mk-5 HE assembly using a Type D pit, and used a betatron for external initiation (the third such test). Total device weight was 2700 lb, predicted yield was 15-20 kt.”
NB: Some people doubt about the authenticity of the video, and believe it to be filmed later and edited heavily.


This is not intended to be an exhaustive glossary. You will find answers to many of your questions by using a search engine. However, here are a few ATLAS physics terms explained to start you off.
|Describes the angle of a particle relative to the beam axis.
|Azimuth angle (φ)
|Describes the angle of a particle measured from the x-axis, around the beam.
|Are like snap-shots, tracing the paths of particles produced in a collision.
|In general, a particle can decay in several modes or decay channels. For example, a Z boson can decay into a pair of neutrinos, a pair of charged leptons, or a pair of quarks (i.e., all the standard model fermions lighter than half the Z mass). The probability for a Z to decay into a neutrino pair is about 20%, into a pair of charged leptons (electrons, muons, or taus) is about 10%, and into a pair of quarks (u,d,c,s,b) is about 70%. These probabilities are called branching fractions.
|The decay channel signifies a certain route a physics process has taken. For example, the W boson may decay to either a pair of hadrons or a pair of leptons. The signature for these W bosons in the detector are therefore either two hadrons or two leptons.
|Electron Volt (eV)
|One electron volt is equal to ~1.6 x 10-19 joules. MeV (106) and TeV (1012) are units of energy used in particle physics. 1 TeV is about the energy of motion of a flying mosquito.
|Subatomic particle having the same mass as one of the particles of ordinary matter but opposite electric charge and magnetic moment.
|Average number of particle interactions per bunch-crossing.


McStas instrument for simulating the GEM diffractometer at ISIS TS1.
Author: E. Farhi, G. Cuello, M. Tucker
Date: September 20, 2006
McStas instrument for simulating GEM at ISIS TS1.
The sample is a powder. The detector is simplified as a banana shaped one.
The General Materials Diffractometer is a new generation neutron diffractometer
recently constructed at the ISIS pulsed neutron source. GEM can be used to
perform high intensity, high resolution experiments to study the structure of
disordered materials and crystalline powders.
Parameters in boldface are required;
the others are optional.


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