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Sensitivity and uncertainty analysis of the VENUS-F critical core

VENUS-F臨界炉心の感度解析・不確かさ解析

岩元 大樹; Stankovskiy, A.*; Uyttenhove, W.*

Iwamoto, Hiroki; Stankovskiy, A.*; Uyttenhove, W.*

A sensitivity and uncertainty analysis was performed for a critical configuration of the VENUS-F facility with three major nuclear data libraries (JENDL-4.0, ENDF/B-VII.1, and JEFF-3.1.2) and the JENDL-4.0 covariance data. Differences in $$k_{rm eff}$$ between nuclear data libraries are smaller than those between geometric models/calculation methodologies. Both the deterministic and Monte-Carlo methodologies in criticality calculation provide similarity for differences in $$k_{rm eff}$$ between the nuclear data libraries. Major contributors to these differences were identified with the sensitivity method. Among nuclear data parameters, it is found that $$k_{rm eff}$$ of the VENUS-F core is sensitive to the fission cross section, fission neutron multiplicity, and capture cross section of uranium and the elastic scattering cross section and average cosine of the scattered neutron of lead and $$^{56}$$Fe. The analysis with the sensitivity coefficients shows that these parameters have considerable impact on the differences in $$k_{rm eff}$$. Based on the JENDL-4.0 covariance data, the total uncertainty induced by nuclear data is evaluated at 833 pcm (1$$sigma$$), and this uncertainty in $$k_{rm eff}$$ is largely dominated by lead, uranium, and $$^{56}$$Fe.

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