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GO CHIBA,MASASHI TSUJI,TADASHINARABAYASHI 한국원자력학회 2014 Nuclear Engineering and Technology Vol.46 No.3
In order to properly quantify fission reactor neutronics parameter uncertainties, we have to use covariance data andsensitivity profiles consistently. In the present paper, we establish two consistent methodologies for uncertainty quantification:a self-shielded cross section-based consistent methodology and an infinitely-diluted cross section-based consistentmethodology. With these methodologies and the covariance data of uranium-238 nuclear data given in JENDL-3.3, wequantify uncertainties of infinite neutron multiplication factors of light water reactor and fast reactor fuel cells. While aninconsistent methodology gives results which depend on the energy group structure of neutron flux and neutron-nuclidereaction cross section representation, both the consistent methodologies give fair results with no such dependences