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Report No.

Reactor physics experiment on a graphite-moderated core to construct integral experiment database for HTGR

Okita, Shoichiro  ; Fukaya, Yuji   ; Sakon, Atsushi*; Sano, Tadafumi*; Takahashi, Yoshiyuki*; Unesaki, Hironobu*

In this paper, integral experiments on a graphite-moderated core were conducted at the B-rack of the Kyoto University Criticality Assembly in order to develop an integral experiment database for the applicability of data assimilation techniques to the neutronic design of a high-temperature gas-cooled reactor. The calculation/experiment-1 (C/E-1)values for the $$k_{rm eff}$$ values at critical cores with the major nuclear data libraries, such as JENDL-4.0, JENDL-5, JEFF-3.2, ENDF/B-VII.1, and ENDF/B-VIII.0, were calculated for the core. Of these, the $$k_{rm eff}$$ values with JENDL-5 with thermal neutron scattering law data for 30% porous graphite showed the best agreement with experimental values within 0.02% accuracy.



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Category:Nuclear Science & Technology



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