PWR Medium Break LOCA source term analysis using ASTEC code
نویسندگان
چکیده
منابع مشابه
Estimation of LOCA Break Size Using Cascaded Fuzzy Neural Networks
Operators of nuclear power plants may not be equipped with sufficient information during a loss-of-coolant accident (LOCA), which can be fatal, or they may not have sufficient time to analyze the information they do have, even if this information is adequate. It is not easy to predict theprogressionof LOCAs innuclear power plants. Therefore, accurate informationon theLOCAbreakpositionandsize sh...
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ژورنال
عنوان ژورنال: Progress in Nuclear Energy
سال: 2015
ISSN: 0149-1970
DOI: 10.1016/j.pnucene.2015.01.001