A midloop operation benchmark test of the RELAP5/MOD3.2 code /
A midloop operation test was performed in 1992 at the BETHSY
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| Format: | Thesis eBook |
| Language: | English |
| Published: |
[Place of publication not identified] :
[publisher not identified] ;
1997.
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| Subjects: | |
| Online Access: | Link to OAKTrust copy |
| Summary: | A midloop operation test was performed in 1992 at the BETHSY and temperature profiles, entrainment phenomena in the upper and upper plenum. Large mass errors were generated by the around 20% of the total system mass by the end of the assess the performance of thermal hydraulic codes under the but did not describe more specific thermal hydraulic bypass, pressurizer manway, and steam generator manway. The code predicted well the timing of the core uncovery and conditions of low pressure and decay heat. The specific conducted experimentally at the BETHSY facility and assess errors in the prediction of component thermal hydraulic head bypass and mass flow ratios between the upper head in terms of predicting macroscopic trends and their timing, in the pressurizer and at the steam generator. In included predicting water holdup cycles in the pressurizer, Integral Test Facility in Grenoble, France. The purpose of integrated mass flow rate, and the emptying of the hot leg its ability to accurately predict the observed phenomena. maximum core heater cladding temperature, and the integrated of these good predictions was the result of compensating participation with the International Standard Problem #38, phasic mass flow rates at the steam generator manway. Some phenomena accurately. Specific areas of disagreement phenomena. The consequence of the poor code performance in predicting the pressurizer/pressurizer surge line phenomena pressurization, an underestimation of the pressurizer RELAP5/MOD3.2.1.1 release of this code. Typical errors were removal system in a midloop operation with manways vents open scenario of the test involved the loss of the residual heat The overall conclusion is that the code performed quite well the RELAP5/MOD3.2 code was used to simulate the transient this experiment was to produce data that could be used to transient. two-phase mixture levels in the guide tube, upper core void was a substantial delay in the falloff of the initial system |
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| Item Description: | "Major subject: Nuclear Engineering". Vita. |
| Physical Description: | xi, 112 leaves : illustrations ; 28 cm. Also available online. Issued also on microfiche from Lange Micrographics. |
| Bibliography: | Includes bibliographical references. |