第58卷第3期2024年3月原子能科学技术AtomicEnergyScienceandTechnologyVol.58,No.3Mar.2024钠冷快堆燃料元件性能分析程序的开发与验证陈启董，高付海（中国原子能科学研究院核工程设计研究所，北京102413）摘要：为了评估钠冷快堆氧化物燃料元件稳态、瞬态和事故条件下的性能和行为演化，开发了钠冷快堆燃料元件性能分析程序FIBER。程序采用有限体积法实现燃料元件温度的计算，用有限元方法实现力学、裂变气体释放的计算，并通过时间步长控制模块控制程序的稳定运行。为验证程序的准确性，通过调研得到俄罗斯BN600反应堆辐照数据，与FIBER程序的裂变气体释放、柱状晶粒等计算结果进行对比分析。结果表明，FIBER程序对最大燃耗11.8at%、最大辐照损伤78dpa的快堆燃料元件的辐照变形、柱状晶区、裂变气体释放性能评价是有效的。关键词：钠冷快堆；燃料元件；燃料元件程序中图分类号：TL334doi:10.7538/yzk.2023.youxian.0477DevelopmentandVerificationofPerformanceAnalysisCodeforFuelElementofSodium-cooledFastReactor(DepartmentofNuclearEngineeringDesign,ChinaInstituteofAtomicEnergy,Beijing102413,China)Abstract:Formanyyears,sodium-cooledfastreactorshaveoccupiedthemostimpor-tantpartoftheclosedfuelcycle.Inordertoimprovetheeconomyofsodium-cooledfastreactors,thenuclearindustryaroundtheworldisactivelyincreasingfuelburnupasmuchaspossible.Thebehaviorsimulationoffuelelementsunderhighfuelburnupisakeyissueinthedesignandreliabilityoffuelelements.Inthiscase,itisnecessarytodevelopcomputercodethatcanaccuratelyanalyzefuelbehaviortoevaluatethebehaviorandreliabilityofhigh-fuelfuels,andasasafetyanalysistooltoevaluatetheperform-anceandbehavioralevolutionoffuelelementsundersteady-state,transientandaccidentconditions.Fortheabovereasons,theChineseInstituteofAtomicEnergyhasdevel-opedFIBER,aperformanceanalysiscodeforfuelelementsofsodium-cooledfastreac-tor.Thecodeconsistsoftwomainparts:Thefirstpartisusedtoanalyzethetempera-turedistribution,thethermaldeformationandfissiongasrelease;Theotherpartisusedtoanalyzethemechanicalbehavioroffuelelements.Inthethermalanalysispart,theaxisymmetricfinitevolumemethodisappliedtotheentirelengthofthefuelelement.文献标志码：ACHENQido...
