Application of MCNP Code in Shielding Calculation of Minitype Fast Reactor
-
摘要: 应用MCNP程序为微型钠冷快堆(MFR)概念设计建立了精确的屏蔽计算模型,并对其主要屏蔽物理量进行详细的计算分析。结果表明:在到达屏蔽层的外边界前,MFR内γ光子和中子注量率都已经迅速下降到较低的水平,主容器外的屏蔽层材料以碳钢为主,可以设计出满足安全准则的屏蔽结构;一回路钠的活化十分有限,屏蔽比较简单,铍反射层中氦的产量和控制棒吸收段的10B消耗比例都很小,这些材料可以使用多个寿期。Abstract: An accurate shielding calculation model has been set up for the minitype sodium-cooled fast reactor (MFR) based on MCNP code and particular calculation of its primary shielding parameters has been carried out. The results indicate that the photon and neutron flux density of MFR has rapidly fallen to a low-level. The material for the shielding layer outside of main container is primarily of carbon steel, which can be design as a shielding structure satisfing the safety code. The sodium activation in primary circuit is extremely limited and it is simple to shield from. Both the output of helium in reflecter and burn up of boron-10 in control rod are very small. These materials can be used for several cycle lives.
-
Key words:
- Minitype fast-neutron reactor /
- Shielding calculation /
- MCNP code
-
计量
- 文章访问数: 3
- HTML全文浏览量: 1
- PDF下载量: 0
- 被引次数: 0