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Simulation of the Primary-Secondary Leak Experiment of IAEA’ Third Standard Problem Exercise Using the RELAP5/MOD2 and RELAP5/MOD3 Computer Codes

Y. A. Hassan, Parvez Salim

Nuclear Technology / Volume 96 / Number 2 / November 1991 / Pages 139-146

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34600

The International Atomic Energy Agency’s third standard problem exercise (SPE-3) is simulated with the RELAP5/MOD2 and RELAP5/MOD3 computer codes. The SPE-3 consists of the simulation of the transient resulting from an 11.9% break in the hot collector of the steam generator (primary-secondary leak) of the PMK-NVH test facility. The predicted scenario is compared with the experimental data. Generally, a reasonable agreement between the code predictions and experimental data is obtained. One important calculated parameter that demonstrates deviation from the data is the break mass flow rate. The RELAP5/MOD2 and RELAP5/MOD3 predictions did not display significant differences. This assessment is a part of an international effort for codes/benchmarks.