Advanced nuclear reactor safety analysis : the simulation of a small break loss of coolant accident in the simplified boiling water reactor using RELAP5/MOD3.1.1 /
(GE) in their Standard Safety Analysis Report (SAR) for the
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| Format: | Thesis eBook |
| Language: | English |
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[Place of publication not identified] :
[publisher not identified] ;
1995.
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| Subjects: | |
| Online Access: | Link to OAKTrust copy |
| Summary: | (GE) in their Standard Safety Analysis Report (SAR) for the accident, and the code's ability to accurately predict the accidents phenomena was investigated. The overall conclusion appearing near the end of the calculation suggest the need by disabling the plant's isolation condenser system and as an code to accurately model low flow, condensation heat experimental data from test facilities is needed to validate flow and heat transfer data calculated by the RELAP5 code flow rates, recirculation ratio, and mass balance were within for further investigation. Both containment temperature and guillotine shear of the vessel's 2 inch bottom drain line I% of those specified in the SAR. However the ability of the initial condition, the loss of site power. The ability of interactive nature of the transient, suggest Additional justified. The uniqueness of the plant's design and the maintained, but that no quantitative significance could be of the plant. Calculated steady state parameters for power, parameters within specifications supplied by General Electric pressure were increasing when the transient was terminated. Reactor plant. The model of the plant was subjected to a reflect expected values and relational interactions are safety related parameters were exceeded, certain trends small break loss of coolant accident occurring from a term of investigation (I 5,500 real time seconds). While no the calculations. the plant's passive safety systems to respond to this type of The RELAP5 code was able to simulate a representative model The thermal hydraulic simulation code RELAP5/MOD3.1.1 was to pass an intuitive engineering inspection. That is to say, transfer, in the presence of noncondensable gases should be utilized to model General Electric's Simplified Boiling Water verified. It is concluded that the simulation's results seem was that the modeled plant maintained all relevant safety while operating at full power. The accident was compounded |
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| Item Description: | "Major subject: Nuclear Engineering". In title, numerals are used. Vita. |
| Physical Description: | xii, 92 leaves : illustrations ; 28 cm. Also available online. Issued also on microfiche from Lange Micrographics. |
| Bibliography: | Includes bibliographical references. |