University of North Texas Libraries, UNT Digital Library, Ĭrediting UNT Libraries Government Documents Department. Modeling operator actions during a small break loss-of-coolant accident in a Babcock and Wilcox nuclear power plant, oai/?verb=GetRecord&metadataPrefix=oai_dc&identifier=info:ark/67531/metadc1069724 For a conservative analysis of the accident, the loss of power to the NPP and failure of one accumulator, and also of two emergency core cooling systems (ECCS). International Image Interoperability Framework (IIIF) US20210210221A1 Nuclear fuel core and methods of fueling and/or defueling a nuclear reactor, control rod drive system for nuclear reactor. Despite incidents like the 1994 loss of coolant accident. This paper presents the method for modeling the operator actions and discusses the simulated accident scenario from the viewpoint of operator actions. Nuclear power plants use fuel rods filled with ceramic pellets of radioactive uranium, usually uranium-235. They agreed that, in general, the modeled operator actions conform to the requirements set forth in the EOPs and are therefore plausible. To assess the credibility of the modeled operator actions, these actions and results of the simulated accident scenario were presented to operator examiners who are familiar with B W nuclear power plants. Different sequences of operator actions are possible for a given accident because of the subjective decisions the operator must make when determining the status of the plant, hence, which branch of the EOP to follow. The sequence of operator actions modeled here is only one of several possibilities. Operator actions were modeled based on the emergency operating procedures (EOPs) and the Technical Bases Document for the EOPs. Comparisons between scoping runs with minimal operator action, and full operator action, clearly showed that the operator plays a key role in recovering the plant. Thus, the small break was further aggravated by reduced HPI flow. The break was initiated by severing one high pressure injection (HPI) line at the cold leg. This work was performed as part of the United States Regulatory Commission's (USNRC) Code, Scaling, Applicability and Uncertainty (CSAU) study. A small break loss-of-accident (SBLOCA) in a typical Babcock and Wilcox (B W) nuclear power plant was modeled using RELAP5/MOD3.
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