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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
NWMO to select Canadian repository site this year
Canada’s Nuclear Waste Management Organization, a not-for-profit organization responsible for the long-term management of the country’s intermediate- and high-level radioactive waste, is set to select a site for a deep geologic repository by the end of the year.
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.