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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.
W. Ullrich, W. Frisch
Nuclear Technology | Volume 41 | Number 2 | December 1978 | Pages 185-194
Technical Paper | Extraction of Energy From Nuclear Fuels Without Reprocessing to Separate Plutonium / Reactor | doi.org/10.13182/NT78-A32104
Articles are hosted by Taylor and Francis Online.
A detailed study of anticipated transients without scram (ATWS) has been carried out in the Federal Republic of Germany based on a boiling water reactor (BWR) and a pressurized water reactor (PWR) reference plant. The study includes transient calculations as well as reliability analyses of the entire scram system (sensors, logic, actuating system). In addition, the influence of other safety related systems (pressure relief system, pump control system in a BWR) has been evaluated. During all ATWS, system pressure does not exceed 110% of design pressure. Only for short periods (several seconds) and only in small areas of the core might film boiling occur. The availability of the scram systems for both a BWR and a PWR is on the order of 10−5 per demand. From these results it is concluded that no independent second scram system is necessary. However, the detailed analysis has given an indication of where hardware measures could be taken to mitigate the transients (e.g., increase of valve capacity) or further improve the availability of the scram system.