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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Feinstein Institutes to research novel radiation countermeasure
The Feinstein Institutes for Medical Research, home of the research institutes of New York’s Northwell Health, announced it has received a five-year, $2.9 million grant from the National Institutes of Health to investigate the potential of human ghrelin, a naturally occurring hormone, as a medical countermeasure against radiation-induced gastrointestinal syndrome (GI-ARS).
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.