核动力工程
覈動力工程
핵동력공정
NUCLEAR POWER ENGINEERING
2009年
6期
15-18,23
,共5页
李云召%吴宏春%曹良志%彭思涛%卢皓亮%宋小明%姚栋
李雲召%吳宏春%曹良誌%彭思濤%盧皓亮%宋小明%姚棟
리운소%오굉춘%조량지%팽사도%로호량%송소명%요동
溶液堆%燃料管理计算%三角形节块方法S_N%FMSR
溶液堆%燃料管理計算%三角形節塊方法S_N%FMSR
용액퇴%연료관리계산%삼각형절괴방법S_N%FMSR
Solution reactor%Fuel management calculation%Triangular node method S_N%FMSR
溶液型医用同位素生产堆的核燃料呈流动的水溶液形式.堆芯呈非结构、强各向异性散射,运行过程中会产生大量气体.针对堆芯燃料管理计算需要在线提取核素等特点,基于以三角形节块S_N方法为模型的中子输运计算程序DNTR,开发了溶液堆堆芯燃料管理计算程序FMSR,并利用该程序对溶液堆进行了模拟分析.结果表明,FMSR程序可在溶液堆堆芯燃料管理计算中试用.
溶液型醫用同位素生產堆的覈燃料呈流動的水溶液形式.堆芯呈非結構、彊各嚮異性散射,運行過程中會產生大量氣體.針對堆芯燃料管理計算需要在線提取覈素等特點,基于以三角形節塊S_N方法為模型的中子輸運計算程序DNTR,開髮瞭溶液堆堆芯燃料管理計算程序FMSR,併利用該程序對溶液堆進行瞭模擬分析.結果錶明,FMSR程序可在溶液堆堆芯燃料管理計算中試用.
용액형의용동위소생산퇴적핵연료정류동적수용액형식.퇴심정비결구、강각향이성산사,운행과정중회산생대량기체.침대퇴심연료관리계산수요재선제취핵소등특점,기우이삼각형절괴S_N방법위모형적중자수운계산정서DNTR,개발료용액퇴퇴심연료관리계산정서FMSR,병이용해정서대용액퇴진행료모의분석.결과표명,FMSR정서가재용액퇴퇴심연료관리계산중시용.
Solution reactor, as a new type of medical isotopes production reactor, is with many special features, such as flowing aqueous fissile solution, unstructured geometry, strong anisotropic scattering, and isotopes distillation. They all raise serious challenges for the fuel management calculation of solution reactors. An in-core fuel management calculation program package for solution reactors, called FMSR, is developed based on the DNTR code, a three-dimensional discrete ordinate nodal transport calculation code in triangular meshes. All results calculated by FMSR, including the distribution of power and void and cycle length and coefficients of reactivity, show that the program package can be used for the in-core fuel management calculation of solution reactors as a trial.