Effect of PWR Cladding Materials in Different Nuclear Evaluated Data Libraries on Reactivity and Its Analysis

Xiao Xiang; Chen Yixue; Yang Tongrui; Wu Jun

Volume 41 Issue 6

Dec. 2020

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Article Navigation > Nuclear Power Engineering > 2020 > 41(6): 24-30

LU Feng, CHEN Mingya, WU Hong, HUANG Ping. Calculation and Discussion of Pressure-Temperature Limit Curves Based on RCCM Code[J]. Nuclear Power Engineering, 2012, 33(6): 1-5.

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Xiao Xiang, Chen Yixue, Yang Tongrui, Wu Jun. Effect of PWR Cladding Materials in Different Nuclear Evaluated Data Libraries on Reactivity and Its Analysis[J]. Nuclear Power Engineering, 2020, 41(6): 24-30.

LU Feng, CHEN Mingya, WU Hong, HUANG Ping. Calculation and Discussion of Pressure-Temperature Limit Curves Based on RCCM Code[J]. Nuclear Power Engineering, 2012, 33(6): 1-5.

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Effect of PWR Cladding Materials in Different Nuclear Evaluated Data Libraries on Reactivity and Its Analysis

Publish Date: 2020-12-15

Abstract

Abstract

Pressurized water reactor cladding material, Nuclear evaluated data library, NJOY2016

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