An evaluation of neutron fluence at reactor pressure vessel using TORT and MCNP codes

被引：0

作者：

Kim, JK ^{[1
]}

Shin, CH ^{[1
]}

Park, SH ^{[1
]}

Kim, JO ^{[1
]}

Kwon, TJ ^{[1
]}

机构：

[1] Hanyang Univ, Seoul 133791, South Korea

来源：

PROCEEDINGS OF THE TOPICAL MEETING ON RADIATION PROTECTION FOR OUR NATIONAL PRIORITIES: MEDICINE, THE ENVIRONMENT, AND THE LEGACY | 2000年

关键词：

D O I：

暂无

中图分类号：

X [环境科学、安全科学];

学科分类号：

08 ; 0830 ;

摘要：

Neutron fluence distributions at reactor pressure vessel (RPV) of the KORI unit 1 were evaluated by using 3-D discrete ordinates (S-N) code, TORT1 and Monte Carlo code, MCNP.(2) The results of TORT and MCNP calculations show a well agreement over all points. TORT gives almost same results as homogeneous MCNP calculations. TORT succeeds in calculation of 3-D RPV fluence without applying synthesis method. TORT run was faster with factor of 4 than MCNP for the same 3-D calculation. This work shows that TORT is a good solving tool in 3-D deep penetrating problem.

引用

页码：261 / 264

页数：4

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