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Title:A COMPARATIVE STUDY ON THE GRAPHITE-MODERATED REACTORS USING DIFFERENT EVALUATED NUCLEAR DATA
DOI No:10.1142/9789812773401_0030
Source:NUCLEAR DATA NEEDS FOR GENERATION IV NUCLEAR ENERGY SYSTEMS (pp 278-283)
Author(s):DO HEON KIM
Korea Atomic Energy Research Institute, P.O. Box 105, Yuseong, Daejeon, 305-600, Korea

C.-S. GIL
Korea Atomic Energy Research Institute, P.O. Box 105, Yuseong, Daejeon, 305-600, Korea

Y.-S. CHO
Korea Atomic Energy Research Institute, P.O. Box 105, Yuseong, Daejeon, 305-600, Korea

Y.-O. LEE
Korea Atomic Energy Research Institute, P.O. Box 105, Yuseong, Daejeon, 305-600, Korea

J. CHANG
Korea Atomic Energy Research Institute, P.O. Box 105, Yuseong, Daejeon, 305-600, Korea

Abstract:The benchmark calculations for several graphite-moderated reactors have been performed by the Monte Carlo code MCNP4C using the libraries based on the ENDF/B-VI.8, JENDL-3.3 and JEFF-3.0. The calculation results for each library have been compared with the experimental values. The isotopic contributions to the keff calculation have been estimated to clarify the causes of the differences among the three libraries.
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