Development of Low-Activation Reinforced Concrete Design Methodology - II: Concrete Activation Analyses of BWR/PWR
NUCLEAR TECHNOLOGY(2009)
Abstract
A precise method for estimating residual radioactivity and decommissioning cost is indispensable when deciding whether to adopt low-activation material. For this precise estimation, accurate estimation of both the thermal neutron flux and the activation cross section of the structural material is necessary. We developed a new groupwise cross-section library that has ten thermal groups for S-N transport calculation and activation calculation. These libraries are tested and used for advanced boiling water reactor (ABWR) and advanced pressurized water reactor (APWR) activation analyses.
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Key words
residual radioactivity,MATXSLIB-J33T10,DORT
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