{"title":"含钍燃料的模块化高温气冷堆数值模拟","authors":"M. Oettingen, J. Cetnar","doi":"10.2478/nuka-2021-0020","DOIUrl":null,"url":null,"abstract":"Abstract The volumetric homogenization method for the simplified modelling of modular high-temperature gas-cooled reactor core with thorium-uranium fuel is presented in the paper. The method significantly reduces the complexity of the 3D numerical model. Hence, the computation time associated with the time-consuming Monte Carlo modelling of neutron transport is considerably reduced. Example results comprise the time evolutions of the effective neutron multiplication factor and fissionable isotopes (233U, 235U, 239Pu, 241Pu) for a few configurations of the initial reactor core.","PeriodicalId":19467,"journal":{"name":"Nukleonika","volume":null,"pages":null},"PeriodicalIF":0.7000,"publicationDate":"2021-11-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"10","resultStr":"{\"title\":\"Numerical modelling of modular high-temperature gas-cooled reactors with thorium fuel\",\"authors\":\"M. Oettingen, J. Cetnar\",\"doi\":\"10.2478/nuka-2021-0020\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"Abstract The volumetric homogenization method for the simplified modelling of modular high-temperature gas-cooled reactor core with thorium-uranium fuel is presented in the paper. The method significantly reduces the complexity of the 3D numerical model. Hence, the computation time associated with the time-consuming Monte Carlo modelling of neutron transport is considerably reduced. Example results comprise the time evolutions of the effective neutron multiplication factor and fissionable isotopes (233U, 235U, 239Pu, 241Pu) for a few configurations of the initial reactor core.\",\"PeriodicalId\":19467,\"journal\":{\"name\":\"Nukleonika\",\"volume\":null,\"pages\":null},\"PeriodicalIF\":0.7000,\"publicationDate\":\"2021-11-25\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"10\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Nukleonika\",\"FirstCategoryId\":\"101\",\"ListUrlMain\":\"https://doi.org/10.2478/nuka-2021-0020\",\"RegionNum\":4,\"RegionCategory\":\"物理与天体物理\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q4\",\"JCRName\":\"CHEMISTRY, INORGANIC & NUCLEAR\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nukleonika","FirstCategoryId":"101","ListUrlMain":"https://doi.org/10.2478/nuka-2021-0020","RegionNum":4,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q4","JCRName":"CHEMISTRY, INORGANIC & NUCLEAR","Score":null,"Total":0}
Numerical modelling of modular high-temperature gas-cooled reactors with thorium fuel
Abstract The volumetric homogenization method for the simplified modelling of modular high-temperature gas-cooled reactor core with thorium-uranium fuel is presented in the paper. The method significantly reduces the complexity of the 3D numerical model. Hence, the computation time associated with the time-consuming Monte Carlo modelling of neutron transport is considerably reduced. Example results comprise the time evolutions of the effective neutron multiplication factor and fissionable isotopes (233U, 235U, 239Pu, 241Pu) for a few configurations of the initial reactor core.
期刊介绍:
"Nukleonika" is an international peer-reviewed, scientific journal publishing original top quality papers on fundamental, experimental, applied and theoretical aspects of nuclear sciences.
The fields of research include:
radiochemistry, radiation measurements, application of radionuclides in various branches of science and technology, chemistry of f-block elements, radiation chemistry, radiation physics, activation analysis, nuclear medicine, radiobiology, radiation safety, nuclear industrial electronics, environmental protection, radioactive wastes, nuclear technologies in material and process engineering, radioisotope diagnostic methods of engineering objects, nuclear physics, nuclear reactors and nuclear power, reactor physics, nuclear safety, fuel cycle, reactor calculations, nuclear chemical engineering, nuclear fusion, plasma physics etc.