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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
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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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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.
H. J. Diamond, W. G. Lee
Nuclear Technology | Volume 54 | Number 3 | September 1981 | Pages 385-392
First International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT81-A32784
Articles are hosted by Taylor and Francis Online.
During 1980, RETRAN was used to simulate the reactor core response characteristics during the Peach Bottom 2 beginning of cycle 5 main steam relief valve (SRV) discharge tests. The SRV tests were conducted at power (50% power) for the purpose of demonstrating that the torus structural response with the “Tee” quencher design is less severe than the structural response predicted by the plant unique torus analysis. In comparison with the measured plant transient data, RETRAN predicted accurate reactor power and pressure trends and magnitudes during both the opening (depressurization) and closing (overpressurization) of the SRVs. Based on these results, it is evident that the RETRAN code and the RETRAN Peach Bottom plant model provide reasonable simulation of mild over/underpres-surization transient events. For the subject analysis, RETRAN 01 Mod 2 was implemented.