Evaluation of Korean Next Generation Reactor Vessel Neutron Fluence by Full-Scope Monte Carlo Calculations
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Date
1999-08-15T00:00:00+00:00
Authors
Jong Kyung Kim
Bo Kyun Seo
Chang Ho Shin
Jae-Hun Lee
Advisors
Journal Title
Series/Report No.
D - Life Prediction including Operating Feed-Back Experience
D06 -
SMiRT 15 - Seoul, South Korea. August 15-20, 1999
D06 -
SMiRT 15 - Seoul, South Korea. August 15-20, 1999
Journal ISSN
Volume Title
Publisher
IASMiRT
