Open AccessIn-vessel coolability and retention of a core melt. Volume 1
Author(s) -
T.G. Theofanous,
C. Liu,
S.L. Additon,
S. Angelini,
O. Kymaelaeinen,
T. Salmassi
Publication year - 1996
Language(s) - English
Resource type - Reports
DOI - 10.2172/491623
Subject(s) - accident management , reactor pressure vessel , parametric statistics , flooding (psychology) , nuclear engineering , cabin pressurization , reliability engineering , reliability (semiconductor) , computer science , bounding overwatch , sensitivity (control systems) , environmental science , power (physics) , engineering , mechanical engineering , mathematics , physics , psychology , statistics , quantum mechanics , artificial intelligence , electronic engineering , psychotherapist
The efficacy of external flooding of a reactor vessel as a severe accident management strategy is assessed for an AP600-like reactor design. The overall approach is based on the Risk Oriented Accident Analysis Methodology (ROAAM), and the assessment includes consideration of bounding scenarios and sensitivity studies, as well as arbitrary parametric evaluations that allow the delineation of the failure boundaries. Quantification of the input parameters is carried out for an AP600-like design, and the results of the assessment demonstrate that lower head failure is physically unreasonable. Use of this conclusion for any specific application is subject to verifying the required reliability of the depressurization and cavity-flooding systems, and to showing the appropriateness (in relation to the database presented here, or by further testing as necessary) of the thermal insulation design and of the external surface properties of the lower head, including any applicable coatings. The AP600 is particularly favorable to in-vessel retention. Some ideas to enhance the assessment basis as well as performance in this respect, for applications to larger and/or higher power density reactors are also provided