Roberto Pergreffi , Francesco Lodi , Giacomo Grasso , Alessia Di Francesco
{"title":"A neutronic model to find promising candidates as burnable poisons in fast reactors","authors":"Roberto Pergreffi , Francesco Lodi , Giacomo Grasso , Alessia Di Francesco","doi":"10.1016/j.pnucene.2025.105940","DOIUrl":null,"url":null,"abstract":"<div><div>Small modular liquid-metal-cooled fast reactors may require dedicated provisions to reach very long core lifetime, or to reduce the reactivity swing if minimizing control requirements is needed. In such cases, the use of burnable poisons may be a necessary route. Unfortunately, to date very few materials are known that may be used as burnable poisons in fast reactors. Goal of this paper is therefore to propose a model by which the expected neutronic behavior of a candidate burnable poison material in fast spectrum can be estimated without the need for extensive neutronic calculations, for which a detailed description of the system in terms of materials and geometry would be required. The neutronic behavior of a material is estimated by considering separately its performance in terms of poisonousness, defined as the ability to provide enough negative reactivity to compensate for the initial excess reactivity of the fuel, from its performance in terms of burnability, defined as the ability to balance in time the reactivity change due to fuel depletion. Although the values calculated by the model equations do not have physical meaning per se, they can be used to compare different materials with each other in order to make a preliminary assessment of their neutronic behavior. The model was first tested with seven candidates (Eu<sub>2</sub>O<sub>3</sub>, Gd<sub>2</sub>O<sub>3</sub>, Dy<sub>2</sub>O<sub>3</sub>, Er<sub>2</sub>O<sub>3</sub>, NpO<sub>2</sub>, AmO<sub>2</sub> and B<sub>4</sub>C), and then assessed against the results obtained from simulations with MCNP6.1 for a lead fast reactor fuel assembly with UO<sub>2</sub> enriched in <sup>235</sup>U at 19.75 wt% in which, one at a time, the various candidates have been added. Despite some small differences from the simulations especially at low burnups, the comparison confirmed the prediction capability of the model up to a poison content of 10 at.%.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"189 ","pages":"Article 105940"},"PeriodicalIF":3.2000,"publicationDate":"2025-07-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Progress in Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0149197025003385","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
Small modular liquid-metal-cooled fast reactors may require dedicated provisions to reach very long core lifetime, or to reduce the reactivity swing if minimizing control requirements is needed. In such cases, the use of burnable poisons may be a necessary route. Unfortunately, to date very few materials are known that may be used as burnable poisons in fast reactors. Goal of this paper is therefore to propose a model by which the expected neutronic behavior of a candidate burnable poison material in fast spectrum can be estimated without the need for extensive neutronic calculations, for which a detailed description of the system in terms of materials and geometry would be required. The neutronic behavior of a material is estimated by considering separately its performance in terms of poisonousness, defined as the ability to provide enough negative reactivity to compensate for the initial excess reactivity of the fuel, from its performance in terms of burnability, defined as the ability to balance in time the reactivity change due to fuel depletion. Although the values calculated by the model equations do not have physical meaning per se, they can be used to compare different materials with each other in order to make a preliminary assessment of their neutronic behavior. The model was first tested with seven candidates (Eu2O3, Gd2O3, Dy2O3, Er2O3, NpO2, AmO2 and B4C), and then assessed against the results obtained from simulations with MCNP6.1 for a lead fast reactor fuel assembly with UO2 enriched in 235U at 19.75 wt% in which, one at a time, the various candidates have been added. Despite some small differences from the simulations especially at low burnups, the comparison confirmed the prediction capability of the model up to a poison content of 10 at.%.
期刊介绍:
Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field.
Please note the following:
1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy.
2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc.
3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.