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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.
Judith K. Hohorst, Chris M. Allison
Nuclear Technology | Volume 98 | Number 2 | May 1992 | Pages 149-159
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34670
Articles are hosted by Taylor and Francis Online.
The SCDAP/RELAP5 severe accident analysis computer code, developed at the Idaho National Engineering Laboratory, is used to analyze the fourth in a series of debris formation experiments. The debris formation-four (DF-4) experiment deals with heatup and meltdown of a boiling water reactor (BWR)-representative fuel and control blade assembly segment, performed in the Annular Core Research Reactor at Sandia National Laboratories. The DF-4 experiment provides data that are used to validate core damage progression and BWR-specific models to gain an understanding of the phenomena occurring in the bundle during a severe BWR accident and to identify additional modeling needed in severe accident codes. The SCDAP/RELAP5 model used for this analysis accurately predicts the key damage events, which include control blade melting, channel box relocation and runaway oxidation, the order and timing of these events, and the maximum bundle temperature. From these analytical calculations, an accident scenario and insights into phenomena occurring during a severe BWR accident are developed.
