In the context of nuclear reactors, a safety code is a computer program used to analyze the safety of a reactor, or to simulate possible accident conditions.
 | This article appears to be a dictionary definition .(May 2023) |
In the context of nuclear reactors, a safety code is a computer program used to analyze the safety of a reactor, or to simulate possible accident conditions.
| | This article appears to be a dictionary definition .(May 2023) |
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A nuclear reactor is a device used to initiate and control a fission nuclear chain reaction or nuclear fusion reactions. Nuclear reactors are used at nuclear power plants for electricity generation and in nuclear marine propulsion. Heat from nuclear fission is passed to a working fluid, which in turn runs through steam turbines. These either drive a ship's propellers or turn electrical generators' shafts. Nuclear generated steam in principle can be used for industrial process heat or for district heating. Some reactors are used to produce isotopes for medical and industrial use, or for production of weapons-grade plutonium. As of 2022, the International Atomic Energy Agency reports there are 422 nuclear power reactors and 223 nuclear research reactors in operation around the world.
A boiling water reactor (BWR) is a type of light water nuclear reactor used for the generation of electrical power. It is the second most common type of electricity-generating nuclear reactor after the pressurized water reactor (PWR), which is also a type of light water nuclear reactor.
A safety-critical system (SCS) or life-critical system is a system whose failure or malfunction may result in one of the following outcomes:
The Jožef Stefan Institute is the largest research institute in Slovenia. The main research areas are physics, chemistry, molecular biology, biotechnology, information technologies, reactor physics, energy and environment. At the beginning of 2013 the institute had 962 employees, of whom 404 were PhD scientists.
Neutron transport is the study of the motions and interactions of neutrons with materials. Nuclear scientists and engineers often need to know where neutrons are in an apparatus, in what direction they are going, and how quickly they are moving. It is commonly used to determine the behavior of nuclear reactor cores and experimental or industrial neutron beams. Neutron transport is a type of radiative transport.
Atomic Energy of Canada Limited (AECL) is a Canadian federal Crown corporation and Canada's largest nuclear science and technology laboratory. AECL developed the CANDU reactor technology starting in the 1950s, and in October 2011 licensed this technology to Candu Energy.
A mission critical factor of a system is any factor that is essential to business operation or to an organization. Failure or disruption of mission critical factors will result in serious impact on business operations or upon an organization, and even can cause social turmoil and catastrophes.
Indira Gandhi Centre for Atomic Research(IGCAR) is one of India's premier nuclear research centres. It is the second largest establishment of the Department of Atomic Energy (DAE), next to Bhabha Atomic Research Centre (BARC), located at Kalpakkam, 80 km south of Chennai, India. It was established in 1971 as an exclusive centre dedicated to the pursuit of fast reactor science and technology, due to the vision of Dr. Vikram Sarabhai. Originally, it was called as Reactor Research Centre (RRC). It was renamed as Indira Gandhi Centre for Atomic Research(IGCAR) by the then Prime Minister of India, Rajiv Gandhi in December 1985. The centre is engaged in broad-based multidisciplinary programme of scientific research and advanced engineering directed towards the development of Fast Breeder Reactor technology, in India.
The AP1000 is a nuclear power plant designed and sold by Westinghouse Electric Company. The plant is a pressurized water reactor with improved use of passive nuclear safety and many design features intended to lower its capital cost and improve its economics.
CRAC-II is both a computer code and the 1982 report of the simulation results performed by Sandia National Laboratories for the Nuclear Regulatory Commission. The report is sometimes referred to as the CRAC-II report because it is the computer program used in the calculations, but the report is also known as the 1982 Sandia Siting Study or as NUREG/CR-2239. The computer program MACCS2 has since replaced CRAC-II for the consequences of radioactive release.
Scram: A Nuclear Power Plant Simulation is an Atari 8-bit family game written by Chris Crawford and published by Atari, Inc. in 1981. Written in Atari BASIC, Scram uses differential equations to simulate nuclear reactor behavior. The player controls the valves and switches of the reactor directly with the joystick.
Carolinas–Virginia Tube Reactor (CVTR), also known as Parr Nuclear Station, was an experimental pressurized tube heavy water nuclear power reactor at Parr, South Carolina in Fairfield County. It was built and operated by the Carolinas Virginia Nuclear Power Associates. CVTR was a small test reactor, capable of generating 17 megawatts of electricity. It was officially commissioned in December 1963 and left service in January 1967.
The State-of-the-Art Reactor Consequence Analyses (SOARCA) is a study of nuclear power plant safety conducted by the Nuclear Regulatory Commission. The purpose of the SOARCA is assessment of possible impact on population caused by major radiation accidents that might occur at NPPs. This new study updates older studies with the latest state-of-the-art computer models and incorporates new plant safety and security enhancements.
The United States Navy job rating of electronics technician (ET) is a designation given by the Bureau of Naval Personnel (BUPERS) to enlisted members who satisfactorily complete initial Electronics Technician "A" school training.
MALPAS is a software toolset that provides a means of investigating and proving the correctness of software by applying a rigorous form of static program analysis. The tool uses directed graphs and regular algebra to represent the program under analysis. Using the automated tools in MALPAS an analyst can describe the structure of a program, classify the use made of data and provide the information relationships between input and output data. It also supports a formal proof that the code meets its specification.
RELAP5-3D is a simulation tool that allows users to model the coupled behavior of the reactor coolant system and the core for various operational transients and postulated accidents that might occur in a nuclear reactor. RELAP5-3D can be used for reactor safety analysis, reactor design, simulator training of operators, and as an educational tool by universities. RELAP5-3D was developed at Idaho National Laboratory to address the pressing need for reactor safety analysis and continues to be developed through the United States Department of Energy and the International RELAP5 Users Group (IRUG) with over $3 million invested annually. The code is distributed through INL's Technology Deployment Office and is licensed to numerous universities, governments, and corporations worldwide.
The vulnerability of nuclear plants to deliberate attack is of concern in the area of nuclear safety and security. Nuclear power plants, civilian research reactors, certain naval fuel facilities, uranium enrichment plants, fuel fabrication plants, and even potentially uranium mines are vulnerable to attacks which could lead to widespread radioactive contamination. The attack threat is of several general types: commando-like ground-based attacks on equipment which if disabled could lead to a reactor core meltdown or widespread dispersal of radioactivity; external attacks such as an aircraft crash into a reactor complex, or cyber attacks.
The Radiation Safety Information Computational Center (RSICC) is a U.S. Department of Energy Specialized Information Analysis Center (SIAC) authorized to collect, analyze, maintain, and distribute computer software and data sets in the areas of radiation transport and safety. The RSICC is operated by Oak Ridge National Laboratory in Oak Ridge, Tennessee. The primary sponsors of the RSICC are the U.S. Department of Energy, the U.S. Department of Homeland Security, and the U.S. Nuclear Regulatory Commission.