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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Deep Space: The new frontier of radiation controls
In commercial nuclear power, there has always been a deliberate tension between the regulator and the utility owner. The regulator fundamentally exists to protect the worker, and the utility, to make a profit. It is a win-win balance.
From the U.S. nuclear industry has emerged a brilliantly successful occupational nuclear safety record—largely the result of an ALARA (as low as reasonably achievable) process that has driven exposure rates down to what only a decade ago would have been considered unthinkable. In the U.S. nuclear industry, the system has accomplished an excellent, nearly seamless process that succeeds to the benefit of both employee and utility owner.
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.
