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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
Standards Program
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.
Virgil E. Schrock
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 323-331
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32334
Articles are hosted by Taylor and Francis Online.
Heating from the decay of radioactive nuclides in shutdown reactors plays an important role in the safety evaluation of nuclear power plants. Although there are many other important uses for this information, the need for more accurate data for the analysis of hypothetical reactor accident scenarios has been the main impetus for recent research activity that has led to a major revision of the Draft American Nuclear Society 5.1 Standard, “Decay Energy Release Rates Following Shutdown of Uranium Fueled Reactors” (published in 1971). The 1978 revised standard, titled “Decay Heat Power in Light Water Reactors,” is based on new experiments and summation calculations. Very accurate determination of the decay heat is now possible for light water reactors, especially within the first 101 s after shutdown, where the influence of neutron capture in fission products may be treated as a small correction to the idealized zero capture case. The new standard accounts for differences among fuel nuclides. It covers cooling times to 109 s, but provides only an “upper bound” on the capture correction in the interval from 104 to 109 s.