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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
Rahim Nabbi
Nuclear Technology | Volume 64 | Number 1 | January 1984 | Pages 5-13
Technical Paper | Nuclear Safety | doi.org/10.13182/NT84-A33321
Articles are hosted by Taylor and Francis Online.
The core dynamic analysis of an anticipated heat removal transient without scram in a high-temperature gas-cooled reactor has indicated that in case of a failure of core cooling, the reactor undergoes a selfshutdown after 1 min because of its negative temperature coefficients of reactivity. If the decay heat removal system operates according to plant specification, recriticality, and thus nuclear power generation, occurs. However, the maximum rise in fuel elements temperature is limited to 50°C due to the high heat capacity of the core. Without taking into consideration the effect of xenon feedback on the neutron kinetics, a new steady core state is established after 2 h in which the fuel temperature and gas outlet temperature at the lower core edge are 195°C higher than in normal operation. Due to transient xenon poisoning, a rise in gas outlet temperature only occurs during the first 70 min and amounts to 70°C. For this reason undesirable transient strains on the components connected behind the core are not expected. A slow xenon buildup during the first hour ensures a long-term subcriticality of the reactor. Without any contribution from the shutdown system, this leads to a decrease in nuclear power and thus to core cooling with functioning decay heat removal.