{"title":"Optimizing spent nuclear fuel cask loading for VVER-440 fuel","authors":"M. Lovecký, J. Závorka","doi":"10.1016/j.net.2024.07.014","DOIUrl":null,"url":null,"abstract":"The paper explores the management of spent nuclear fuel, focusing on dual-purpose spent fuel casks used to store and transport spent nuclear fuel from VVER-440 reactors. The main goal is to optimize spent fuel cask loading by developing an extensive methodology supported by a powerful tool. Using a multiple-zoning strategy, cooler outside fuel assemblies protect radiation sources from the hotter inner assemblies. An effective tool based on adjoint particle flux calculations is the recently developed OPOS-440 calculation code. This code allows for optimizing the loading pattern and determining dose rates surrounding the spent nuclear fuel cask for a selected fuel loading. The code also thoroughly demonstrates how different fuel assemblies affect the dose rate. These findings have real-world implications for reactor operations, including optimizing cask loading and supporting the licensing procedure for novel fuel types in already-existing spent fuel casks.","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":null,"pages":null},"PeriodicalIF":2.6000,"publicationDate":"2024-07-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Technology","FirstCategoryId":"5","ListUrlMain":"https://doi.org/10.1016/j.net.2024.07.014","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
The paper explores the management of spent nuclear fuel, focusing on dual-purpose spent fuel casks used to store and transport spent nuclear fuel from VVER-440 reactors. The main goal is to optimize spent fuel cask loading by developing an extensive methodology supported by a powerful tool. Using a multiple-zoning strategy, cooler outside fuel assemblies protect radiation sources from the hotter inner assemblies. An effective tool based on adjoint particle flux calculations is the recently developed OPOS-440 calculation code. This code allows for optimizing the loading pattern and determining dose rates surrounding the spent nuclear fuel cask for a selected fuel loading. The code also thoroughly demonstrates how different fuel assemblies affect the dose rate. These findings have real-world implications for reactor operations, including optimizing cask loading and supporting the licensing procedure for novel fuel types in already-existing spent fuel casks.
期刊介绍:
Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters.
NET covers all fields for peaceful utilization of nuclear energy and radiation as follows:
1) Reactor Physics
2) Thermal Hydraulics
3) Nuclear Safety
4) Nuclear I&C
5) Nuclear Physics, Fusion, and Laser Technology
6) Nuclear Fuel Cycle and Radioactive Waste Management
7) Nuclear Fuel and Reactor Materials
8) Radiation Application
9) Radiation Protection
10) Nuclear Structural Analysis and Plant Management & Maintenance
11) Nuclear Policy, Economics, and Human Resource Development