Evaluation of Korean Next Generation Reactor Vessel Neutron Fluence by Full-Scope Monte Carlo Calculations

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Title: Evaluation of Korean Next Generation Reactor Vessel Neutron Fluence by Full-Scope Monte Carlo Calculations
Author: Jong Kyung Kim; Bo Kyun Seo; Chang Ho Shin; Jae-Hun Lee
Publisher: IASMiRT
Date: 1999-08-15
Series/Report No.: D - Life Prediction including Operating Feed-Back Experience
D06 -
SMiRT 15 - Seoul, South Korea. August 15-20, 1999
URI: http://www.lib.ncsu.edu/resolver/1840.20/30023


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