Simulation of the loss of the residual heat removal of an integral test facility using computer code Cathare7 /
2775 thermal NM Framatome Pressurized Water Reactor (PWR).
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| Format: | Thesis eBook |
| Language: | English |
| Published: |
[Place of publication not identified] :
[publisher not identified] ;
1996.
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| Subjects: | |
| Online Access: | Link to OAKTrust copy |
| Summary: | 2775 thermal NM Framatome Pressurized Water Reactor (PWR). against experimental data. The thermal hydraulic CATHARE Assessment of the ability of thermal hydraulic codes to back to rnidloop level. The transient was executed on the BETHSY is an integral test facility modeling the three-loop, CATHARE code and of the physical basis of PWR Emergency caused by CATHARE's miscalculation of the phase separation code's predictions were in a qualitative agreement with the cold water was actuated in the cold leg when cladding conducted at BETHSY Integral Test Facility located in correctly predict complex phenomena during reactor during the initial stage of the transient. This was probably effect at the hot leg/surge line tee junction and significant experimental data. experimental simulation of the loss of the Residual Heat Grenoble, France. HP6400 workstation at Texas A&M University. The code International Standard Problem (ISP38) experiment Its main objectives are to contribute to the assessment of needs to be refined for the low pressure range. Overall, the opening of the pressurizer manway and the steam generator Operating Procedures. This investigation dealt with outlet plenum manway simultaneously with switching on the ovepredicted mass discharge through steain generator manway power of heating rods, thus simulating loss of the RHRS. The predictions underestimated the time of the core uncovery and Removal System (RHRS) during midloop operation. It involved temperature at the top of heating rods reached 250 C. The test was stopped when the primary cooling system was filled test. It was found that the model of the upward tee junction the actuation of the gravity feed injection due to the throughout the test. Mass discharge through both manways led to core boiling and uncovery. A gravity feed injection of total power was kept unchanged with the level 138 kW transients can be performed only by means of comparison V1.3U computer program has been used to simulate water entrainment into the surge line in the beginning of the |
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| Item Description: | "Major subject: Nuclear Engineering". Vita. |
| Physical Description: | x, 53 leaves : illustrations ; 28 cm. Also available online. Issued also on microfiche from Lange Micrographics. |
| Bibliography: | Includes bibliographical references: 51-52. |