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使用MCNP程序验证ADS的设计 被引量:1

Validation of Accelerator Driven Subcritical Reactors Utilizing MCNP Code
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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keff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。 In this paper, some characteristics of the ADS subcritical reactor core is described using the Monte Carlo code(MCNP). The keff 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.
出处 《核动力工程》 EI CAS CSCD 北大核心 2013年第4期12-15,共4页 Nuclear Power Engineering
关键词 ADS MCNP程序 KEFF 铋合金 ADS, MCNP Code,Keffe, Lead, Lead-bismuth alloy
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