{"title":"Understanding kinetic behaviour of TRIGA reactor core","authors":"Rashida Yasmeen, M. S. Mahmood","doi":"10.1504/IJNEST.2017.10009091","DOIUrl":null,"url":null,"abstract":"The kinetic parameters govern the transient behaviour of a nuclear reactor. Estimation of these parameters has great importance for the safe design and operation of a nuclear reactor. In order to understand the kinetic behaviour of TRIGA core, the influence of graphite dummy elements, absorber materials and beam ports on kinetic parameters has been studied. To do so, the effective delayed neutron fraction (βeff), prompt removal lifetime (e) and mean neutron generation time (Λ) have been calculated for an infinite system of LEU fuel cells. The investigation has been extended to four different cases of TRIGA reactor core. Monte Carlo simulation has been carried out to compute the kinetic parameters by Monte Carlo code MCNP5. The βeff value remains unchanged but the e and Λ values are found to be sensitive to the local perturbations of core components.","PeriodicalId":35144,"journal":{"name":"International Journal of Nuclear Energy Science and Technology","volume":"11 1","pages":"265"},"PeriodicalIF":0.0000,"publicationDate":"2017-11-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"International Journal of Nuclear Energy Science and Technology","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1504/IJNEST.2017.10009091","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q4","JCRName":"Energy","Score":null,"Total":0}
引用次数: 0
Abstract
The kinetic parameters govern the transient behaviour of a nuclear reactor. Estimation of these parameters has great importance for the safe design and operation of a nuclear reactor. In order to understand the kinetic behaviour of TRIGA core, the influence of graphite dummy elements, absorber materials and beam ports on kinetic parameters has been studied. To do so, the effective delayed neutron fraction (βeff), prompt removal lifetime (e) and mean neutron generation time (Λ) have been calculated for an infinite system of LEU fuel cells. The investigation has been extended to four different cases of TRIGA reactor core. Monte Carlo simulation has been carried out to compute the kinetic parameters by Monte Carlo code MCNP5. The βeff value remains unchanged but the e and Λ values are found to be sensitive to the local perturbations of core components.
期刊介绍：
Today, nuclear reactors generate nearly one quarter of the electricity in nations representing two thirds of humanity, and other nuclear applications are integral to many aspects of the world economy. Nuclear fission remains an important option for meeting energy requirements and maintaining a balanced worldwide energy policy; with major countries expanding nuclear energy"s role and new countries poised to introduce it, the key issue is not whether the use of nuclear technology will grow worldwide, even if public opinion concerning safety, the economics of nuclear power, and waste disposal issues adversely affect the general acceptance of nuclear power, but whether it will grow fast enough to make a decisive contribution to the global imperative of sustainable development.
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