Verification of nuclear data libraries used to design molten salt blankets of a fusion neutron source

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2024-10-21 DOI:10.1016/j.anucene.2024.110983

Yu.E. Titarenko, S.A. Balyuk, V.F. Batyaev, V.I. Belousov, I.A. Bedretdinov, V. Yu. Blandinskiy, V.D. Davidenko, I.I. Dyachkov, V.M. Zhivun, Ya.O. Zaritstkiy, M.V. Ioannisian, A.S. Kirsanov, A.A. Kovalishin, N.A. Kovalenko, B.V. Kuteev, V.O. Legostaev, M.R. Malkov, I.V. Mednikov, K.V. Pavlov, A. Yu. Titarenko, K.G. Chernov

{"title":"Verification of nuclear data libraries used to design molten salt blankets of a fusion neutron source","authors":"Yu.E. Titarenko, S.A. Balyuk, V.F. Batyaev, V.I. Belousov, I.A. Bedretdinov, V. Yu. Blandinskiy, V.D. Davidenko, I.I. Dyachkov, V.M. Zhivun, Ya.O. Zaritstkiy, M.V. Ioannisian, A.S. Kirsanov, A.A. Kovalishin, N.A. Kovalenko, B.V. Kuteev, V.O. Legostaev, M.R. Malkov, I.V. Mednikov, K.V. Pavlov, A. Yu. Titarenko, K.G. Chernov","doi":"10.1016/j.anucene.2024.110983","DOIUrl":null,"url":null,"abstract":"<div><div>This study presents the results of testing nuclear data libraries by analyzing statistical criteria obtained from comparing experimental and calculated rates for (n,2n), (n,p), (n,pn), (n,nꞌγ) (n,α) and (n,γ) reactions measured on samples <sup>nat</sup>Ni, <sup>nat</sup>Zr, <sup>nat</sup>Nb, <sup>nat</sup>Cd, <sup>nat</sup>Ti, <sup>nat</sup>Co,<sup>63(96%), 65(99.70%)</sup>Cu, <sup>64(99.70%)</sup>Zn, <sup>nat</sup>In, <sup>nat</sup>Al, <sup>nat</sup>Mg, <sup>nat</sup>Fe, <sup>nat</sup>Au and <sup>nat</sup>Th, which were placed in the experimental channels of micromodels of the fusion blanket.</div><div>The “fast” (the cylinder Ø 230 mm and 520 mm length was filled with ∼ 67 kg of molten salt 0.52NaF + 0.48ZrF4) and the “thermal” blanket (the same cylinder was placed in a dry channel inside a cubic container filled with water with dimensions of 52.0 × 52.0 × 52.0 cm were investigated. The reaction rates were measured using the activation method.</div><div>Modeling with transport codes MCNP5, KIR, PHITS-3.31, SuperMC3.4.0 was performed using the ENDF/B-VII.0 library for neutron transport as well as seven neutron data libraries for reaction rates simulation, including: JEFF-3.3, JENDL-4.0, ENDF/B–VIII.0, ROSFOND-2010, FENDL-3.0, TENDL − 2019 and IRDFF-II.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":null,"pages":null},"PeriodicalIF":1.9000,"publicationDate":"2024-10-21","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/S0306454924006467","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}

引用次数: 0

Abstract

This study presents the results of testing nuclear data libraries by analyzing statistical criteria obtained from comparing experimental and calculated rates for (n,2n), (n,p), (n,pn), (n,nꞌγ) (n,α) and (n,γ) reactions measured on samples ^natNi, ^natZr, ^natNb, ^natCd, ^natTi, ^natCo,^{63(96%), 65(99.70%)}Cu, ^64(99.70%)Zn, ^natIn, ^natAl, ^natMg, ^natFe, ^natAu and ^natTh, which were placed in the experimental channels of micromodels of the fusion blanket.

The “fast” (the cylinder Ø 230 mm and 520 mm length was filled with ∼ 67 kg of molten salt 0.52NaF + 0.48ZrF4) and the “thermal” blanket (the same cylinder was placed in a dry channel inside a cubic container filled with water with dimensions of 52.0 × 52.0 × 52.0 cm were investigated. The reaction rates were measured using the activation method.

Modeling with transport codes MCNP5, KIR, PHITS-3.31, SuperMC3.4.0 was performed using the ENDF/B-VII.0 library for neutron transport as well as seven neutron data libraries for reaction rates simulation, including: JEFF-3.3, JENDL-4.0, ENDF/B–VIII.0, ROSFOND-2010, FENDL-3.0, TENDL − 2019 and IRDFF-II.

查看原文本刊更多论文

验证用于设计聚变中子源熔盐毯的核数据库

本研究介绍了核数据图书馆的测试结果，方法是分析通过比较以下反应的实验率和计算率获得的统计标准：(n,2n)、(n,p)、(n,pn)、(n,nꞌγ)(n,α)和(n,γ)，这些反应是在 natNi、natZr、natNb、natCd、natTi、natCo、63(96%)、65(99.70%)Cu、64(99.70%)Zn、natIn、natAl、natMg、natFe、natAu 和 natTh 样品上测量的。快速"（直径为 230 毫米、长度为 520 毫米的圆柱体中装有 67 公斤的熔盐 0.研究了 "快速"（在直径为 230 毫米、长度为 520 毫米的圆筒中装入约 67 公斤的熔盐 0.52NaF + 0.48ZrF4 ）和 "热 "毯（将同一圆筒置于装满水的立方体容器内的干燥通道中，容器尺寸为 52.0 × 52.0 × 52.0 厘米）。使用 MCNP5、KIR、PHITS-3.31、SuperMC3.4.0 等传输代码建模，使用ENDF/B-VII.0 库进行中子传输，并使用七个中子数据库进行反应速率模拟，包括JEFF-3.3、JENDL-4.0、ENDF/B-VIII.0、ROSFOND-2010、FENDL-3.0、TENDL - 2019 和 IRDFF-II。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

求助全文

约1分钟内获得全文求助全文

来源期刊

Annals of Nuclear Energy 工程技术-核科学技术

CiteScore

4.30

自引率

21.10%

发文量

632

审稿时长

7.3 months

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.