Đ. Petrović , A. Rineiski , M. Zanetti , G. Scheveneels , X.-N. Chen , William D’haeseleer
{"title":"重液态金属快堆发生急临界事故时的中子动力学及低能中子的重要性","authors":"Đ. Petrović , A. Rineiski , M. Zanetti , G. Scheveneels , X.-N. Chen , William D’haeseleer","doi":"10.1016/j.anucene.2024.110975","DOIUrl":null,"url":null,"abstract":"<div><div>Accidental scenarios that involve degradation of a fast reactor core and/or relocation of its fuel material call for particular attention with respect to promptcritical reactivity events. The dynamics of a power transient during such an event is governed by the Prompt Neutron Generation Time (PNGT), a parameter that is sensitive to the moderating power of the system. Since Heavy Liquid Metals (HLMs) have a boiling point that is higher than the melting point of stainless steel, the first degradation mechanism to occur in a Heavy Liquid Metal Fast Reactor (HLMFR) is likely to be the loss of structural material. This sequence holds the potential to create conditions for considerable spectrum softening and may thus have important implications for the value of the PNGT. In the framework of this study, a (postulated) complete absence of structural material in and around the reactor core of an HLMFR is demonstrated to lead to an increase in the PNGT by an order of magnitude.</div><div>The sensitivity of the fission energy release during a promptcritical event to the value of the PNGT is further investigated by employing the severe accident code SIMMER-III. To correctly model a degraded reactor core characterized by a considerably softer neutron spectrum when compared to the spectrum of its intact configuration, a new neutron data set is generated. This is done by introducing new energy groups to the already existing 11-energy-group structure and collapsing multigroup cross-section data by employing a weighting spectrum representative of a degraded core configuration of an HLMFR. Subsequent simulations demonstrate that an increase in the PNGT by a factor of ∼4 yields an increase in the fission energy release during a Core Disruptive Accident (CDA) by ∼50 %. It is therefore established that low-energy neutrons may play an important role during a promptcritical reactivity transient in an HLMFR.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":null,"pages":null},"PeriodicalIF":1.9000,"publicationDate":"2024-10-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"On the Neutron Kinetics during a Promptcritical Accident in a Heavy Liquid Metal Fast Reactor and the Importance of Low-Energy Neutrons\",\"authors\":\"Đ. Petrović , A. Rineiski , M. Zanetti , G. Scheveneels , X.-N. Chen , William D’haeseleer\",\"doi\":\"10.1016/j.anucene.2024.110975\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>Accidental scenarios that involve degradation of a fast reactor core and/or relocation of its fuel material call for particular attention with respect to promptcritical reactivity events. The dynamics of a power transient during such an event is governed by the Prompt Neutron Generation Time (PNGT), a parameter that is sensitive to the moderating power of the system. Since Heavy Liquid Metals (HLMs) have a boiling point that is higher than the melting point of stainless steel, the first degradation mechanism to occur in a Heavy Liquid Metal Fast Reactor (HLMFR) is likely to be the loss of structural material. This sequence holds the potential to create conditions for considerable spectrum softening and may thus have important implications for the value of the PNGT. In the framework of this study, a (postulated) complete absence of structural material in and around the reactor core of an HLMFR is demonstrated to lead to an increase in the PNGT by an order of magnitude.</div><div>The sensitivity of the fission energy release during a promptcritical event to the value of the PNGT is further investigated by employing the severe accident code SIMMER-III. To correctly model a degraded reactor core characterized by a considerably softer neutron spectrum when compared to the spectrum of its intact configuration, a new neutron data set is generated. This is done by introducing new energy groups to the already existing 11-energy-group structure and collapsing multigroup cross-section data by employing a weighting spectrum representative of a degraded core configuration of an HLMFR. Subsequent simulations demonstrate that an increase in the PNGT by a factor of ∼4 yields an increase in the fission energy release during a Core Disruptive Accident (CDA) by ∼50 %. It is therefore established that low-energy neutrons may play an important role during a promptcritical reactivity transient in an HLMFR.</div></div>\",\"PeriodicalId\":8006,\"journal\":{\"name\":\"Annals of Nuclear Energy\",\"volume\":null,\"pages\":null},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2024-10-29\",\"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/S0306454924006388\",\"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/S0306454924006388","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}
On the Neutron Kinetics during a Promptcritical Accident in a Heavy Liquid Metal Fast Reactor and the Importance of Low-Energy Neutrons
Accidental scenarios that involve degradation of a fast reactor core and/or relocation of its fuel material call for particular attention with respect to promptcritical reactivity events. The dynamics of a power transient during such an event is governed by the Prompt Neutron Generation Time (PNGT), a parameter that is sensitive to the moderating power of the system. Since Heavy Liquid Metals (HLMs) have a boiling point that is higher than the melting point of stainless steel, the first degradation mechanism to occur in a Heavy Liquid Metal Fast Reactor (HLMFR) is likely to be the loss of structural material. This sequence holds the potential to create conditions for considerable spectrum softening and may thus have important implications for the value of the PNGT. In the framework of this study, a (postulated) complete absence of structural material in and around the reactor core of an HLMFR is demonstrated to lead to an increase in the PNGT by an order of magnitude.
The sensitivity of the fission energy release during a promptcritical event to the value of the PNGT is further investigated by employing the severe accident code SIMMER-III. To correctly model a degraded reactor core characterized by a considerably softer neutron spectrum when compared to the spectrum of its intact configuration, a new neutron data set is generated. This is done by introducing new energy groups to the already existing 11-energy-group structure and collapsing multigroup cross-section data by employing a weighting spectrum representative of a degraded core configuration of an HLMFR. Subsequent simulations demonstrate that an increase in the PNGT by a factor of ∼4 yields an increase in the fission energy release during a Core Disruptive Accident (CDA) by ∼50 %. It is therefore established that low-energy neutrons may play an important role during a promptcritical reactivity transient in an HLMFR.
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.