THE HEMCNT CODE, A HETEROGENEOUS MONTE-CARLO NEUTRON-TRANSPORT CODE FOR FISSION AND FUSION-REACTOR DESIGNS AND NEUTRON SHIELDING CALCULATIONS

被引：0
|
作者：
CAMPEAU, JC
CHANG, JS
机构：
来源：
10TH ANNUAL CONFERENCE 1989 - CANADIAN NUCLEAR SOCIETY, PROCEEDINGS VOL 3 | 1989年
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D O I：
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中图分类号：
X [环境科学、安全科学];
学科分类号：
08 ; 0830 ;
摘要：
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页码：D36 / D44
页数：9
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