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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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House E&C members question the DOE
As work progresses on the Department of Energy’s Nuclear Reactor Pilot Program, which will progress through DOE authorization rather than Nuclear Regulatory Commission licensing, three members of the House Committee on Energy and Commerce have sent a critical letter to Energy Secretary Chris Wright.
The letter demands “information about the DOE and its employees’ dealings with the NRC and its staff” and expresses concern that DOE staff has “broken the firewall” between the departments.
Wondea Jung
Nuclear Technology | Volume 202 | Number 2 | May-June 2018 | Pages 210-219
Technical Paper | doi.org/10.1080/00295450.2017.1419784
Articles are hosted by Taylor and Francis Online.
Although a feed and bleed (F&B) operation is an important emergency task having a significant effect on the risk of a pressurized water reactor–type nuclear power plant, there is a high uncertainty regarding its modeling and analysis in a probabilistic safety assessment (PSA). This paper introduces a study on the design of an operational strategy for an F&B operation based on human reliability analysis (HRA) with plant-specific thermal-hydraulic (TH) and human performance time (PT) analyses. The emergency operating procedures (EOPs) of a reference plant were modified by adding a new procedural path for the F&B operation to reduce its effect on the plant’s risk. To support the modification of the procedure, an intensive TH analysis was conducted to evaluate the plant’s behavior in diverse accident conditions and to revise the success criteria for the HRA of the F&B operation. In addition, an empirical analysis of PT required to carry out the F&B operation was conducted based on plant-specific simulator records. The PSA model of the reference plant was revised by reflecting the modified EOPs and new success criteria for the HRA of the F&B operation, which showed that core damage frequency of the revised PSA was about 50% lower than that of the original PSA.