An Evaluation of Korean Next Generation Reactor Pressure Vessel Neutron Fluence by Monte Carlo Simulations

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Title: An Evaluation of Korean Next Generation Reactor Pressure Vessel Neutron Fluence by Monte Carlo Simulations
Author: Kim, Jong Kyung; Shin, Chang Ho; Park, Sung-Ho; Park, Goon-Cherl; Lee, Jae-Hun
Publisher: IASMiRT
Date: 2001-08-12
Series/Report No.: S - Advanced Reactors
S01 -
SMiRT 16 - Washington, DC, USA. August 12-17, 2001
URI: http://www.lib.ncsu.edu/resolver/1840.20/30905


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