Benchmark analyses for EBR-II shutdown heat removal tests SHRT-17 and SHRT-45R

• Published in: Nuclear engineering and design 2014-08, Vol.275, p.312-321
• Main Authors: Mochizuki, Hiroyasu, Muranaka, Kohmei, Asai, Takayuki, van Rooijen, W.F.G.
• Format: Article
• Language: English
• ISSN: 0029-5493; 1872-759X
• DOI: 10.1016/j.nucengdes.2014.05.027

•The IAEA EBR-II benchmarks SHRT-17 and SHRT-45R are analyzed with a 1D system code.•The calculated result of SHRT-17 corresponds well to the measured results.•For SHRT-45R ERANOS is used for various core parameters and reactivity coefficients.•SHRT-45R peak temperature is overestimated with the ERANOS feedback coefficients.•The peak temperature is well predicted when the feedback coefficient is reduced. Benchmark problems of several experiments in EBR-II, proposed by ANL and coordinated by the IAEA, are analyzed using the plant system code NETFLOW++ and the neutronics code ERANOS. The SHRT-17 test conducted as a loss-of-flow test is calculated using only the NETFLOW++ code because it is a purely thermal–hydraulic problem. The measured data were made available to the benchmark participants after the results of the blind benchmark calculations were submitted. Our work shows that major parameters of the plant are predicted with good accuracy. The SHRT-45R test, an unprotected loss of flow test is calculated using the NETFLOW++ code with the aid of delayed neutron data and reactivity coefficients calculated by the ERANOS code. These parameters are used in the NETFLOW++ code to perform a semi-coupled analysis of the neutronics – thermal–hydraulic problem. The measured data are compared with our calculated results. In our work, the peak temperature is underestimated, indicating that the reactivity feedback coefficients are too strong. When the reactivity feedback coefficient for thermal expansion is adjusted, good agreement is obtained in general for the calculated plant parameters, with a few exceptions.