Comparative analysis of fuel burnup calculations of fourth-generation European fast reactors

IF 0.4 4区工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY Kerntechnik Pub Date : 2023-08-14 DOI:10.1515/kern-2023-0019

Amr Ibrahim

{"title":"Comparative analysis of fuel burnup calculations of fourth-generation European fast reactors","authors":"Amr Ibrahim","doi":"10.1515/kern-2023-0019","DOIUrl":null,"url":null,"abstract":"Abstract The sustainability of nuclear energy implies the continuous research and development of fast reactor technology. This work represents a comparative analysis of fuel burnup calculations of three commercial-level fast spectrum concepts which are under research and development in Europe. The investigated designs are the European Sodium-cooled Fast Reactor, the European Lead-cooled Fast Reactor, and the European Gas-cooled Fast Reactor. MCNPX transport code was used to design three representative fuel assemblies of these fourth-generation concepts to analyze and compare their neutronic and safety parameters. The neutronic and safety analysis in this work includes the evolution of infinite multiplication factor and fissile inventory, neutron yield, the average energy of neutrons causing fission, neutron energy spectrum, neutron generation time, Doppler reactivity effect, effective delayed neutron fraction, and coolant void reactivity coefficient. The fuel burnup results showed that the ESFR is superior regarding the reactivity swing and breeding of fissile 239Pu. On the other hand, analysis of safety parameters results showed that they depend mainly on fuel composition rather than on other design specifications.","PeriodicalId":17787,"journal":{"name":"Kerntechnik","volume":"6 1","pages":""},"PeriodicalIF":0.4000,"publicationDate":"2023-08-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Kerntechnik","FirstCategoryId":"5","ListUrlMain":"https://doi.org/10.1515/kern-2023-0019","RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q4","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}

引用次数: 0

Abstract

Abstract The sustainability of nuclear energy implies the continuous research and development of fast reactor technology. This work represents a comparative analysis of fuel burnup calculations of three commercial-level fast spectrum concepts which are under research and development in Europe. The investigated designs are the European Sodium-cooled Fast Reactor, the European Lead-cooled Fast Reactor, and the European Gas-cooled Fast Reactor. MCNPX transport code was used to design three representative fuel assemblies of these fourth-generation concepts to analyze and compare their neutronic and safety parameters. The neutronic and safety analysis in this work includes the evolution of infinite multiplication factor and fissile inventory, neutron yield, the average energy of neutrons causing fission, neutron energy spectrum, neutron generation time, Doppler reactivity effect, effective delayed neutron fraction, and coolant void reactivity coefficient. The fuel burnup results showed that the ESFR is superior regarding the reactivity swing and breeding of fissile 239Pu. On the other hand, analysis of safety parameters results showed that they depend mainly on fuel composition rather than on other design specifications.

查看原文

微信好友朋友圈 QQ好友复制链接

本刊更多论文

第四代欧洲快堆燃料燃耗计算的对比分析

核能的可持续性意味着对快堆技术的持续研究和发展。这项工作代表了欧洲正在研究和开发的三个商业级快速频谱概念的燃料消耗率计算的比较分析。所研究的设计是欧洲钠冷快堆、欧洲铅冷快堆和欧洲气冷快堆。采用MCNPX输运代码设计了三个具有代表性的第四代概念燃料组件，并对其中子参数和安全参数进行了分析和比较。本工作的中子和安全分析包括无限增殖因子和裂变库存的演变、中子产生量、引起裂变的中子平均能量、中子能谱、中子产生时间、多普勒反应性效应、有效延迟中子分数和冷却剂空洞反应性系数。燃料燃耗结果表明，ESFR在239Pu的反应性波动和增殖方面具有优越性。另一方面，安全参数分析结果表明，其主要取决于燃料成分，而不是其他设计参数。

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分钟内获得全文去求助

来源期刊

Kerntechnik 工程技术-核科学技术

CiteScore

0.90

自引率

20.00%

发文量

审稿时长

6-12 weeks

期刊介绍： Kerntechnik is an independent journal for nuclear engineering (including design, operation, safety and economics of nuclear power stations, research reactors and simulators), energy systems, radiation (ionizing radiation in industry, medicine and research) and radiological protection (biological effects of ionizing radiation, the system of protection for occupational, medical and public exposures, the assessment of doses, operational protection and safety programs, management of radioactive wastes, decommissioning and regulatory requirements).