使用MCNP程序验证ADS的设计

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Validation of Accelerator Driven Subcritical Reactors Utilizing MCNP Code

1. School of Nuclear Science and Engineering of North China Electric Power University, Beijing, 102206, China;
2. Northwest Institute of Nuclear Technology, Xian, 710024, China

摘要: 利用MCNP程序对加速器驱动次临界系统(ADS)堆芯设计进行验证。在确定堆芯尺寸的情况下,当ADS的靶源和冷却剂是铅、铅-铋合金、铋和汞时,通过MCNP程序进行模拟计算得到相应的k_eff值、中子能谱和中子通量密度;并对铅、铅-铋合金、铋和汞的数据进行对比分析。结果表明,铅-铋合金是ADS系统的最佳材料,根据相应数据,提出堆芯设计的优化方案。
- ADS /
- MCNP程序 /
- k_eff /
- 铅 /
- 铅-铋合金
Abstract: In this paper,some characteristics of the ADS subcritical reactor core is described using the Monte Carlo code（MCNP）.The k_eff value,neutron energy spectrum and neutron flux of a ADS system are obtained by the MCNP code under certain ADS core size as the ADS target and coolant are lead,lead-bismuth alloy,bismuth and mercury respectively.The data and the ADS system parameters obtained from the MCNP simulation calculation are compared and analyzed.The results show that the lead-bismuth alloy is the best material for ADS target and coolant among all the materials tested.
- ADS /
- MCNP Code /
- k_eff /
- Lead /
- Lead-bismuth alloy