Neutronics calculation analysis for china 2×6 helium-cooled solid breeder test blanket module

被引：0

作者：

Han, Jing-Ru ^{[1
]}

Chen, Yi-Xue ^{[1
]}

Lu, Dao-Gang ^{[1
]}

Zhang, Guo-Shu ^{[2
]}

Cao, Qi-Xian ^{[2
]}

机构：

[1] School of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, China

[2] Southwestern Institute of Physics, Chengdu 610041, China

来源：

Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2012年 / 46卷 / 04期

关键词：

Helium-cooled solid breeders - ITER - MCNP - Neutronics - Power density distributions - Test blanket module - Tritium generation rate - Tritium production rate;

D O I：

暂无

中图分类号：

学科分类号：

摘要：

In order to meet the requirement of ITER toroidal field ripple effect, a new design of helium-cooled solid breeder test blanket module (HCSB-TBM) with reduced low activation ferritic martensitic stainless steel (LAFM) was proposed by Southwestern Institute of Physics. By using MCNP code and global ITER MCNP model, 3D neutronics calculations for the new 2×6 HCSB-TBM design were performed and the results of tritium generation rate, nuclear heating deposit and power density distribution were obtained. The tritium production rate is about 12.68 mg/d while considering ITER duty factor of 22%. The TBM total nuclear heating deposit is about 522.5 kW, and the peak power density is 11.8 W/cm3 which appears in Li4SiO4. The results can provide neutronics data for TBM further structural and thermal-hydraulic optimization and design of other systems.

引用

页码：453 / 456

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