Development and abecedarian verification of reactor core physic and thermal-hydraulic analysis software package DCNMC

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机构：
[1] [1,Zhou, Xu-Hua
[2] Cai, Qi
[3] Wang, Deng-Ying
[4] Li, Fu
[5] Yi, Xiong-Ying
来源：
Zhou, X.-H. | 1600年 / Atomic Energy Press卷 / 34期
关键词：
Codes (symbols) - Nuclear energy - Nuclear fuels - Nuclear power plants - Verification;
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摘要：
With a view to the characteristics of the specific type nuclear reactor, five reactor core physic and thermal-hydraulic codes are integrated into the software package as calculation kernel. In the software package, the Dragon code is applied to calculate the homogenized few group constant for fuel assembly, the CITATION code, NGFM code and MCNP code are applied for core physic calculation with different methodology, the COBRA code is applied for core thermal-hydraulic calculation. In addition two homegrown codes named as DOCS and DCNMC are used as data transmission interface tool and calculation management tool.. Then, a generic reactor core physic and thermal-hydraulic analysis software for the specific type nuclear reactor is developed. A calculation model on some reactor core is established. Then, the accuracy of the code system and model is verified, and the results indicate the accuracy meets the requirements.
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