原子能科学技术
原子能科學技術
원자능과학기술
ATOMIC ENERGY SCIENCE AND TECHNOLOGY
2014年
3期
407-411
,共5页
袁龙军%陈义学%韩静茹
袁龍軍%陳義學%韓靜茹
원룡군%진의학%한정여
蒙特卡罗%离散纵标%双向耦合%快中子注量
矇特卡囉%離散縱標%雙嚮耦閤%快中子註量
몽특잡라%리산종표%쌍향우합%쾌중자주량
Monte Carlo%discrete ordinates%bidirectional coupling%fast neutron fluence
蒙特卡罗(MC)-离散纵标(SN )双向耦合方法是解决大型复杂核装置屏蔽问题的有效方法。本文针对三维MC-SN 双向耦合方法在大型压水堆核电站屏蔽计算中的应用,进行了基准验证分析。基于美国核管会(NRC)发布的NUREG/CR-6115压水堆基准模型,采用自主开发的三维MC-SN 双向耦合屏蔽计算分析方法,利用MCNP4C精确计算堆芯到热屏蔽精细模型以及位于压力容器内部计算区域的精确模型,三维SN 程序TORT用于进行热屏蔽到第2下降区外表面间的计算。通过自主研发的接口程序实现MC粒子概率分布与SN 角通量密度间的相互转换,实现MC和SN 双向耦合计算。三维MC-SN双向耦合方法计算结果与基准报告提供的MCNP、DORT结果符合良好,初步验证了该方法解决大型复杂核装置屏蔽问题的可行性。
矇特卡囉(MC)-離散縱標(SN )雙嚮耦閤方法是解決大型複雜覈裝置屏蔽問題的有效方法。本文針對三維MC-SN 雙嚮耦閤方法在大型壓水堆覈電站屏蔽計算中的應用,進行瞭基準驗證分析。基于美國覈管會(NRC)髮佈的NUREG/CR-6115壓水堆基準模型,採用自主開髮的三維MC-SN 雙嚮耦閤屏蔽計算分析方法,利用MCNP4C精確計算堆芯到熱屏蔽精細模型以及位于壓力容器內部計算區域的精確模型,三維SN 程序TORT用于進行熱屏蔽到第2下降區外錶麵間的計算。通過自主研髮的接口程序實現MC粒子概率分佈與SN 角通量密度間的相互轉換,實現MC和SN 雙嚮耦閤計算。三維MC-SN雙嚮耦閤方法計算結果與基準報告提供的MCNP、DORT結果符閤良好,初步驗證瞭該方法解決大型複雜覈裝置屏蔽問題的可行性。
몽특잡라(MC)-리산종표(SN )쌍향우합방법시해결대형복잡핵장치병폐문제적유효방법。본문침대삼유MC-SN 쌍향우합방법재대형압수퇴핵전참병폐계산중적응용,진행료기준험증분석。기우미국핵관회(NRC)발포적NUREG/CR-6115압수퇴기준모형,채용자주개발적삼유MC-SN 쌍향우합병폐계산분석방법,이용MCNP4C정학계산퇴심도열병폐정세모형이급위우압력용기내부계산구역적정학모형,삼유SN 정서TORT용우진행열병폐도제2하강구외표면간적계산。통과자주연발적접구정서실현MC입자개솔분포여SN 각통량밀도간적상호전환,실현MC화SN 쌍향우합계산。삼유MC-SN쌍향우합방법계산결과여기준보고제공적MCNP、DORT결과부합량호,초보험증료해방법해결대형복잡핵장치병폐문제적가행성。
The Monte Carlo (MC)-discrete ordinates (SN ) bidirectional coupling method is an efficient approach to solve shielding calculation of the large complex nuclear facility .The test calculation was taken by the application of the MC-SN bidirectional coupling method on the shielding calculation of the large PWR nuclear facility .Based on the characteristics of NUREG/CR-6115 PWR benchmark model issued by the NRC ,3D Monte Carlo code was employed to accurately simulate the structure from the core to the thermal shield and the dedicated model of the calculation parts locating in the pressure vessel ,while the TORT was used for the calculation from the thermal shield to the second down-comer region .The transform between particle probability distribution of MC and angular flux density of SN was realized by the interface program to achieve the coupling calculation . The calculation results were compared with MCNP and DORT solutions of benchmark report and satisfactory agreements were obtained . The preliminary validity of feasibility by using the method to solve shielding problem of a large complex nuclear device was proved .