蒙特卡罗燃耗计算程序MCNTRANS的开发与验证

本文介绍了开发的蒙特卡罗燃耗计算程序MCNTRANS。MCNTRANS的中子学计算参数直接采用MCNP5程序的反应率计算值,燃耗计算方法采用图论算法跟踪燃耗链,同时,对实际燃耗过程进行详细分析以提高计算精度与程序适用性,并使用预估 校正方法以获取较大的燃耗计算步长。程序计算结果通过OECD/NEA与JAERI燃耗基准题实验结果进行验证,并与其他程序的计算结果进行比较。结果表明,MCNTRANS程序在不同燃耗深度下的计算结果和实验值与其他程序的计算值符合较好,部分锕系核素与裂变产物的计算精度更高。     

基于RELAP5的氦氙流动换热计算模块开发与验证

反应堆热工系统分析程序是开展热工水力计算与安全评价的重要工具。为开发适用于氦氙气冷空间堆的热工系统分析程序,本文在RELAP5/MOD40程序中拓展了氦氙混合气体（He Xe）物性计算模块,添加了适用于He Xe的传热关系式,将拓展后程序计算值与实验值进行对比。结果表明：程序默认的Sutherlands定律用于He Xe物性计算时将引入较大误差;Dittus Bolter公式对He Xe对流换热时的Nu预测偏高,将导致不保守的壁温计算结果。拓展后的程序对He Xe压降和换热计算结果均与实验值吻合较好,验证了程序开发的正确性以及程序用于He Xe流动换热计算的功能。本研究可为系统层面程序开发奠定基础。     

基于OpenMC执行码的编译检测及临界基准验证

开源蒙特卡罗程序OpenMC(OpenMonte Carlo code)只提供源代码而没有执行码,在编译OpenMC的过程中发现不同版本的辅助程序与之存在兼容性问题。本文通过分析OpenMPI、Mpich及HDF5各版本辅助程序,对0.6.2版本OpenMC源代码的支持情况进行研究,为正确编译OpenMC执行码给出了直接参考。为进一步验证OpenMC执行码计算临界问题的正确性,选择国际临界安全基准评价实验手册(The International Criticality Safety Benchmark Evaluation Project,ICSBEP)中的96道代表性例题进行基准校验,与通用蒙特卡罗程序的计算结果进行对比并以实验值作为参考。结果表明,OpenMC计算值与实验值及其他程序计算值吻合较好,验证了OpenMC临界计算的可行性和正确性,上述结论将为程序以后的实际应用及完善奠定基础。     

EBR-Ⅱ无保护失流试验SHRT-45R分析

为验证中国原子能科学研究院自主开发的快堆系统分析程序FASYS,对美国钠冷快堆EBR-Ⅱ的SHRT-45R无保护失流试验进行了计算分析。利用FASYS程序对试验的堆芯和一回路进行建模,以两台一回路主泵的转速、中间热交换器二次侧入口流量和温度作为计算边界条件。通过对比分析计算值与试验值发现,以堆芯功率为输入数据时,泵流量和XX09测量组件冷却剂温度计算值与试验值吻合良好,由于采用点模型模拟堆芯上腔室温度,Z形管道进口温度计算值变化较试验值快。在堆芯功率和温度耦合计算情况下,堆芯功率的计算值与实测功率总体上吻合良好,堆芯相对功率低于10%后计算值略有偏大。FASYS程序对SHRT-45R试验的分析,验证了该程序的堆芯热工水力模型、一回路热工水力模型、点堆模型,特别是反应性反馈模型。     

TP2008核数据库研制

根据最新评价核数据库ENDF/B-Ⅶ的特点,对群常数制作程序系统NJOY97进行了修改,建立了NJOY97CNDC程序系统。并采用NJOY97CNDC程序系统,主要基于ENDF/B-Ⅶ库,研制了与TPFAP程序接口的TP2008核数据库,同时,采用TPFAP-E程序对TP2008库进行了相应的基准检验计算,并将计算结果与基准实验值、TPFAP程序自带库(CPMLIB)的计算值、TP2000库的计算值进行了比较,验证了TP2008库的可靠性。可以看出,TP2008库给出了较好的基准检验计算结果。更全面的工程检验计算,有待于进一步地展开。     

西安脉冲堆计算值和实测结果分析

介绍了西安脉冲堆堆芯布置、计算模型和程序以及计算值与实验测量结果分析。西安脉冲堆在满功率（2MW）下连续运行了72小时，证明西安脉冲堆整个系统和设备是良好的、安全可靠的。根据西安脉冲堆计算值与测量值的比较，证明计算程序可靠，具有较高精度。西安脉冲堆理论计算值与实验测量值符合较好，完全满足工程设计要求，实验测量结果达到了设计指标的要求。     

MCNP程序在反应堆临界计算中的应用

用三维的蒙特卡罗程序（MCNP）进行临界计算，着重介绍堆芯和反射层的建模，利用MCNP程序的重复结构功能简化对堆芯的描述，以JRR3为例计算了几个不同棒位于Keff值，计算结果与参值吻合较好，表明MCNP程序能够用于反应堆的临界计算。     

一维开式自然循环系统分析程序的实验验证

基于华龙一号非能动安全壳热量导出系统（PCS）综合性能实验装置实验结果,对采用基于漂移流模型开发的华龙一号PCS程序（PCS?NCCP）进行验证,对比分析了设计工况及非设计工况下PCS?NCCP程序计算值与实验值之间的误差。结果显示,所开发的PCS?NCCP程序能模拟PCS的排热能力、稳态运行特性和动态响应特性,程序计算值能很好地跟踪实验的趋势和幅值变化,绝大部分计算误差落在±20%范围内,验证了PCS?NCCP程序的准确性。     

60Co辐照装置剂量场均匀性的优化设计

采用蒙特卡罗方法和MATLAB(Matrix Laboratory)程序对由576根钴源构成的辐照装置中剂量场均匀性进行优化设计.首先将程序计算结果与实验测量进行比较,接着对程序设置3200个计算点计算了辐照装置的剂量场分布;剂量场均匀性计算中,不断地改变钴源棒位置并不断计算空间平面剂量场.计算结果发现,程序计算值与实验测量值较为一致,经调整后装置的空间剂量均匀度显著提高,使得辐照装置的能量使用率大大提高.     

系统安全分析程序TSACO的开发与验证

选择用于评估高温气冷堆系统安全分析程序瞬态分析能力的HE-FUS3实验装置为对象,利用自主开发的系统热工水力瞬态分析程序TSACO对其进行建模,并对稳态工况和失流事故进行模拟分析。计算结果表明,稳态工况下系统重要部件温度的TSACO程序计算值与HE-FUS3实验值符合较好,失流事故中系统流量和测试段出口温度的计算值与实验值均符合良好,证明了TSACO程序应用于系统瞬态热工安全分析的可靠性。     

核电子学与核探测技术领域中的计算机应用问题

文中对近十年来核电子学与核探测技术领域内计算机应用的状况作了概括;简要的讨论了能谱数据获取、计算机断层成象、以及大型数据获取等系统方面的技术进展。对值得注意引用的计算机学科内发展起来的一些新技术与新技术产品作了简单的评价。     

The Use of Computers in Nuclear Medicine

Computers are needed in nuclear medicine, they answer a need to avoid loss of patient data and are necessary for image processing which deserves a wider use than it presently enjoys. The computer is nearly essential for dynamic or function studies and its use is due to increase. If a computer is to function effectively in clinical service, the processes it executes must be finished in a very short time. This time constraint means that clinical programs must be assembly language programs rather than slower "higher level" language programs. A computer is near its speed limit while servicing a gamma camera and while processing images. Full use of the computer for nuclear medicine requi'res development of systems providing rapid and reliable image processing and production of hard copy results, of course, at a reasonable cost.     

Nuclear data sheets for A = 64

Nuclear structure data available through March 15, 1979, are evaluated, and adopted level and gamma properties are given. The bulk of the data is presented pictorially for easy comparison. Experimental details, references, comments, and additional data are given in the text. All drawings, tables, and comments are reproduced from the computerized Evaluated Nuclear Structure Data File (ENSDF). Any additions or corrections desired by the users should be addressed to the evaluators for maintenance and updating of the computer file.     

Nuclear data sheets for A = 67

Nuclear structure data available through July 1975 are compiled, and adopted level properties are given. The bulk of the data are presented pictorially for easy comparison. Experimental details, references, and additional comments, where required, are given in the text. All drawings, tables, and comments are reproduced from the computerized Evaluated Nuclear Structure Data File (ENSDF). Any additions or corrections desired by the users should be addressed to the compilers for maintenance and updating of the computer file.     

Nuclear data sheets for A = 65

Nuclear structure data available through July 1975 are compiled, and adopted level properties are given. The bulk of the data are presented pictorially for easy comparison. Experimental details, references, and additional comments, where required, are given in the text. All drawings, tables, and comments are reproduced from the computerized Evaluated Nuclear Structure Data File (ENSDF). Any additions or corrections desired by the users should be addressed to the compilers for maintenance and updating of the computer file.     

Nuclear data sheets for A = 69

Nuclear structure data available through September 1975 are compiled, and adopted level properties are given. The bulk of the data are presented pictorially for easy comparison. Experimental details, references, and additional comments, where required, are given in the text. All drawings, tables, and comments are reproduced from the computerized Evaluated Nuclear Structure Data File (ENSDF). Any additions or corrections desired by the users should be addressed to the compilers for maintenance and updating of the computer file.     

Nuclear data sheets for A = 66

Nuclear structure data available through July 1975 are compiled, and adopted level properties are given. The bulk of the data are presented pictorially for easy comparison. Experimental details, references, and additional comments, where required, are given in the text. All drawings, tables, and comments are reproduced from the computerized Evaluated Nuclear Structure Data File (ENSDF). Any additions or corrections desired by the users should be addressed to the compilers for maintenance and updating of the computer file.     

Nuclear data sheets for A = 50

Nuclear structure data available through May 1976 are compiled, and adopted level properties are given. The bulk of the data are presented pictorially for easy comparison. Experimental details, references, and additional comments, where required, are given in the text. All drawings, tables, and comments are reproduced from the computerized Evaluated Nuclear Structure Data File (ENSDF). Any additions or corrections desired by the users should be addressed to the compilers for maintenance and updating of the computer file.     

Nuclear data sheets for A = 62

Nuclear structure data available through August 1, 1978 are compiled, and adopted level properties are given. The bulk of the data is presented pictorially for easy comparison. Experimental details, references, and additional comments, where required, are given in the text. All drawings, tables, and comments are reproduced from the computerized Evaluated Nuclear Structure Data File (ENSDF). Any additions or corrections desired by the users should be addressed to the evaluators for maintenance and updating of the computer file.     

Nuclear data sheets for A = 53

Nuclear structure data available through April 1977 are compiled, and adopted level properties are given. The bulk of the data is presented pictorially for easy comparison. Experimental details, references, and additional comments, where required, are given in the text. All drawings, tables, and comments are reproduced from the computerized Evaluated Nuclear Structure Data File (ENSDF). Any additions or corrections desired by the users should be addressed to the compilers for maintenance and updating of the computer file.