{"title":"采用两步法和超均质法对研究用反应堆进行中子学分析","authors":"Chixu Luo, Mingrui Yang, Qing Zhu, Chaoyuan Zhang, Xiaojing Liu, Tengfei Zhang","doi":"10.1016/j.anucene.2024.110912","DOIUrl":null,"url":null,"abstract":"<div><p>Research reactors are characterized by significant neutron leakage, tight neutron coupling, and complex core geometries, which make accurate neutronics calculations using the two-step method challenging. This paper analyzes and quantifies the errors introduced by the two-step method for research reactor neutronics calculations. Based on the LVR-15 research reactor, the effects of several key factors, such as the number of energy groups, the homogenization model, and the S<sub>N</sub> order, are studied in detail by comparing the computed <em>k</em><sub>eff</sub> and power with reference values. The numerical results indicate that the factors affecting calculation accuracy, in descending order of impact, are the number of energy groups, the homogenization model, and the S<sub>N</sub> order. The number of energy groups has the most significant impact on calculation accuracy. Specifically, using too few energy groups, such as 2-group energy structures, leads to significant overestimations of <em>k</em><sub>eff</sub>. To further improve accuracy, an improved superhomogenization (SPH) method is proposed. It can stably maintain the <em>k</em><sub>eff</sub> error below 500 pcm and reduce power prediction errors from 3.08 ∼ 4.67 % and 1.69 ∼ 2.80 % to 1.40 ∼ 3.49 % and 0.60 ∼ 1.98 % in the control-rod-in and control-rod-out cases, respectively. These findings provide valuable reference guidelines for other researchers aiming to achieve more accurate research reactor neutronics calculations based on the two-step method.</p></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":null,"pages":null},"PeriodicalIF":1.9000,"publicationDate":"2024-09-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Neutronics analysis of a research reactor using a two-step method with the superhomogenization method\",\"authors\":\"Chixu Luo, Mingrui Yang, Qing Zhu, Chaoyuan Zhang, Xiaojing Liu, Tengfei Zhang\",\"doi\":\"10.1016/j.anucene.2024.110912\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><p>Research reactors are characterized by significant neutron leakage, tight neutron coupling, and complex core geometries, which make accurate neutronics calculations using the two-step method challenging. This paper analyzes and quantifies the errors introduced by the two-step method for research reactor neutronics calculations. Based on the LVR-15 research reactor, the effects of several key factors, such as the number of energy groups, the homogenization model, and the S<sub>N</sub> order, are studied in detail by comparing the computed <em>k</em><sub>eff</sub> and power with reference values. The numerical results indicate that the factors affecting calculation accuracy, in descending order of impact, are the number of energy groups, the homogenization model, and the S<sub>N</sub> order. The number of energy groups has the most significant impact on calculation accuracy. Specifically, using too few energy groups, such as 2-group energy structures, leads to significant overestimations of <em>k</em><sub>eff</sub>. To further improve accuracy, an improved superhomogenization (SPH) method is proposed. It can stably maintain the <em>k</em><sub>eff</sub> error below 500 pcm and reduce power prediction errors from 3.08 ∼ 4.67 % and 1.69 ∼ 2.80 % to 1.40 ∼ 3.49 % and 0.60 ∼ 1.98 % in the control-rod-in and control-rod-out cases, respectively. These findings provide valuable reference guidelines for other researchers aiming to achieve more accurate research reactor neutronics calculations based on the two-step method.</p></div>\",\"PeriodicalId\":8006,\"journal\":{\"name\":\"Annals of Nuclear Energy\",\"volume\":null,\"pages\":null},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2024-09-13\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Annals of Nuclear Energy\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0306454924005759\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0306454924005759","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
Neutronics analysis of a research reactor using a two-step method with the superhomogenization method
Research reactors are characterized by significant neutron leakage, tight neutron coupling, and complex core geometries, which make accurate neutronics calculations using the two-step method challenging. This paper analyzes and quantifies the errors introduced by the two-step method for research reactor neutronics calculations. Based on the LVR-15 research reactor, the effects of several key factors, such as the number of energy groups, the homogenization model, and the SN order, are studied in detail by comparing the computed keff and power with reference values. The numerical results indicate that the factors affecting calculation accuracy, in descending order of impact, are the number of energy groups, the homogenization model, and the SN order. The number of energy groups has the most significant impact on calculation accuracy. Specifically, using too few energy groups, such as 2-group energy structures, leads to significant overestimations of keff. To further improve accuracy, an improved superhomogenization (SPH) method is proposed. It can stably maintain the keff error below 500 pcm and reduce power prediction errors from 3.08 ∼ 4.67 % and 1.69 ∼ 2.80 % to 1.40 ∼ 3.49 % and 0.60 ∼ 1.98 % in the control-rod-in and control-rod-out cases, respectively. These findings provide valuable reference guidelines for other researchers aiming to achieve more accurate research reactor neutronics calculations based on the two-step method.
期刊介绍:
Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.