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IAEA-SPE-1: Pre-Test Calculations for the PMK-NVH Standard Problem Exercise

机译:IaEa-spE-1:pmK-NVH标准问题练习的预测试计算

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摘要

Pre-test calculations of the IAEA Standard Problem Exercise (IAEA-SPE-I) are presented. The experimental basis of the SPE is the PMK-NVH facility, the full-pressure 1:2070 scaled model of the Paks Nuclear Power Plant. The studied transient process was a 7.4% break in the cold leg of the reactor. The analysis was carried out by the KfK version of RELAP4/mod6 code. Major occurrances of the transient are given. 5 references, 47 figures, 9 tables. (ERA citation 12:028653)

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