Study on Selection Method of Shielding Nuclides in Nuclear Reactor Based on Non-Dominated Sorting

IF 0.4 Q4 NUCLEAR SCIENCE & TECHNOLOGY Journal of Nuclear Fuel Cycle and Waste Technology Pub Date : 2022-08-08 DOI:10.1115/icone29-90902
Rui Li, Shichang Liu
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Abstract

In the reactor, the main purpose of radial shielding was to protect the internal structure and staff from radiation damage. The good shielding material must have both a high elastic scattering cross-section and a high absorption cross-section to reduce the radiation level outside the reactor core and ensure the safety of workers and equipment outside the reactor. In this paper, a new type selection scheme of shielding material was proposed, which read the reaction cross-sections of all-natural stable nuclides in the ENDF/B-VII database, calculated the single group cross-sections of various reactions of all nuclides by the integral method according to the neutron energy spectrum. Then ranked the nuclides with different cross-sections as the target, to screen the nuclides with the best neutron and photon shielding effect. In this paper, a typical Monte Carlo particle transport program was used for preliminary verification, which was applied to the energy spectrum of the pressurized water reactor and sodium-cooled fast reactor. The results show that for neutron shielding, photon shielding, and neutron-photon shielding, in the thermal neutron spectrum, the coincidence rates between the non-dominated sorting scheme and the Monte Carlo method were 95 %, 98.95 %, and 94.87 % respectively, and in the fast neutron spectrum, the coincidence rates between the non-dominated sorting scheme and the Monte Carlo method were 72.5 %, 95.79 %, and 82.5 % respectively. The calculation time of non-dominated sorting was less than 3% of that of the Monte Carlo method. It provided an efficient method for the selection of shielding nuclides in advanced reactors and had engineering application significance.
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基于非优势分选的核反应堆屏蔽核素选择方法研究
在反应堆中,径向屏蔽的主要目的是保护内部结构和工作人员免受辐射损害。良好的屏蔽材料必须同时具有高弹性散射截面和高吸收截面,以降低反应堆堆芯外的辐射水平,保证反应堆外工作人员和设备的安全。本文提出了一种新的屏蔽材料选型方案,该方案读取ENDF/B-VII数据库中全天然稳定核素的反应截面,根据中子能谱用积分法计算出所有核素各种反应的单族截面。然后对不同截面的核素进行排序,筛选出屏蔽中子和光子效果最好的核素。本文采用典型的蒙特卡罗粒子输运程序进行了初步验证,并将其应用于压水堆和钠冷快堆的能谱。结果表明,对于中子屏蔽、光子屏蔽和中子-光子屏蔽,在热中子谱中,非主导分选方案与蒙特卡罗方法的符合率分别为95%、98.95%和94.87%;在快中子谱中,非主导分选方案与蒙特卡罗方法的符合率分别为72.5%、95.79%和82.5%。非支配排序的计算时间小于蒙特卡罗方法的3%。为先进反应堆屏蔽核素的选择提供了一种有效的方法,具有工程应用意义。
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来源期刊
CiteScore
0.80
自引率
25.00%
发文量
35
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