液态金属冷却快堆堆芯物理分析软件LoongSARAX的验证与确认

Verification and Validation of LoongSARAX Code for Nuclear Physics Analysis of Liquid Metal Cooled Fast Reactor

  • 摘要: NECP-SARAX是西安交通大学核工程计算物理实验室自主开发的先进反应堆中子学分析计算系统。在此基础上,西安交通大学针对液态金属冷却快堆的堆芯物理工程设计与安全审评,定制开发了LoongSARAX。为了实现LoongSARAX的工程应用,规范性、系统性的验证与确认是该过程的重要一环。为此,本文针对LoongSARAX验证与确认研究,在搜集整理国际上关于液态金属冷却快堆物理计算基准题的基础上,建立了其验证与确认矩阵,并将程序分成不同模块,分别进行了模块验证、子系统验证和系统确认,范围涵盖冷却剂为钠和铅的快堆,如JOYO、ZPPR17A等。程序验证与确认表明LoongSARAX程序对于液态金属冷却快堆具有较高的计算精度,同时针对中国实验快堆(CEFR)开展了不确定度量化研究。结果表明,在99%置信度下,有效增殖因数计算结果的不确定度有90%的概率落在-389 pcm,300 pcm以内。

     

    Abstract: In fourth-generation reactors, fast reactors characterized by high average neutron flux, proliferating fission nuclear fuel, and transmutation of long-decay actinides have become the primary research focus in China. NECP-SARAX is an advanced reactor neutron analysis and calculation system independently developed by the Nuclear Engineering Computational Physics Laboratory of Xi'an Jiaotong University. Based on the features and functions of NECP-SARAX, Xi'an Jiaotong University has developed a customized LoongSARAX system specifically for core physical engineering design and safety evaluation of liquid metal cooled fast reactors. LoongSARAX includes cross-section generation module TULIP and core steady-state analysis module LAVENDER. TULIP is used for the calculation of uniform assemblies, and for addressing one-dimensional plate and cylinder problems. LAVENDER is used for the 3-D core calculation for advanced reactor neutron analysis systems. After obtaining the few-group cross sections for each assembly, LAVENDER employs multi-group neutron transport methods to calculate the core's primary parameters. LAVENDER calculates a variety of parameters for liquid metal cooled fast reactor cores, including criticality, power distribution, reactivity, burnup, etc. In the course of software development, discrepancies between the results obtained through software calculations and actual results are inevitable. If LoongSARAX is to be applied to engineering practice, it is indispensable to ensure its normative and systematic verification and validation (V&V). Relevant international data on the physical calculation benchmark of liquid metal cooled fast reactor were collected and collated in this paper, with a focus on the V&V of LoongSARAX. On this basis, the V&V matrix for the LoongSARAX program was established. In order to improve the accuracy of verification, the whole program was divided into different modules for module verification, subsystem verification and system verification respectively. LoongSARAX was referred to as the system, with TULIP and LAVENDER being its subsystems. The V&V process begins with modules in TULIP and LAVENDER, followed by the system as a whole. The V&V of LoongSARAX covers fast reactors with sodium and lead coolants, such as JOYO, ZPPR17A, FFTF, BFS, etc. By comparing the calculation results of LoongSARAX with the experimental measurement results or MCNP results in the benchmark reports, it can be clearly concluded that LoongSARAX has high calculation accuracy and reliability in the field of liquid metal cooled fast reactor. In summary, LoongSARAX, a computing system developed by Xi'an Jiaotong University for liquid metal cooled fast reactors, demonstrates excellent computing capabilities after undergoing rigorous and systematic V&V. This will provide strong support for the core physical engineering design and safety evaluation of liquid metal cooled fast reactors, and the application of LoongSARAX will also provide valuable experience for the development and promotion of fast reactors in the future.

     

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