Analysis of a research reactor under anticipated transients without scram events using the RELAP5/MOD3.2 computer program /
(2) the non-availability of one pump and 50 %
| Main Author: | |
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| Format: | Thesis eBook |
| Language: | English |
| Published: |
[Place of publication not identified] :
[publisher not identified] ;
1998.
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| Subjects: | |
| Online Access: | Link to OAKTrust copy |
| Summary: | (2) the non-availability of one pump and 50 % (3) the non-availability of all the three heat 270 Kg/s in the first transient and to 133 Kg/s in 6[]C. However, during the simulation of the non- a small, hypothetical, research reactor based on the account for the annular geometry of the fuel elements. annulus. Consequently, temperature in the second fuel at 408.5 seconds into the transient with saturation availability of all the three heat enchanters, primary availability of two of the three heat enchanters and change resulted in the expulsion of fluid from the conditions being attained in the annulus. The phase coolant temperature started increasing rapidly. Void enchanters. To carry out the above simulations, events associated with heat exchanger transients. In flux (CHF) correlations of the RELAP program to generation occurred in the central fuel element annuli High Flux Australian Reador HIFAR using the indicated that the mass flow rate would decrease to modifications were incorporated to the critical heat non-availability of one of the two primary pumps and of one of the three heat enchanters (2) the non- operation of the other pimp. In the second series, RELAPS/MOD3.Z computer program. The first series ring exceeded 800K, resulting in its failure. rise in the central fuel element temperature would be simulated the ATWS events associated with pump Simulations for two series of anticipated transients phics. temperature would be 23[]C. The results of the first temperatures in the primly circuit would be 50C and that the maximum rise in the coolant temperatures in the first series, two cases were simulated: (1) the the maximum rise in the central fuel element the primary circuit would be 18.5[]C and the maximum The results of the simulated plump transients three cases were simulated: (1) the non-availability transient 2. The maximum rise in the coolant transients and the second series simulated the ATWS two cases of the heat exchanger transients indicated without scram (ATWS) events have been carried out for |
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| Item Description: | "Major subject: Nuclear Engineering". Vita. |
| Physical Description: | xiii, 103 leaves : illustrations ; 28 cm. Also available online. |
| Bibliography: | Includes bibliographical references (leaves 99-102). |