利用 MHTGR-350 开发和验证用于 HTGR 分析的多组高级半解析节点法求解器

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2024-08-01 DOI:10.1016/j.anucene.2024.110818
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引用次数: 0

摘要

本研究介绍了为高温气冷堆(HTGR)分析量身定制的多组高级半分析节点法(A-SANM)。A-SANM 是专为具有六边形几何结构的反应堆而设计的,例如伏多-沃达尼能动反应堆(VVER)和高温气冷堆。通过对多项式函数和双曲函数进行积分,构建了一个以 12 项为基础的三角形节点,以划定通量。这种方法的多组计算内核被嵌入了节点扩散代码 RAST-V。为了评估 A-SANM 的计算效率,我们采用了 MHTGR-350 基准。该基准与模块化高温气冷反应堆有关,由经合组织/国家原子能机构于 2021 年在 NGNP 项目下建立。在本研究中,我们进行了第一阶段计算,以评估中子学代码的性能。我们对乘法因子、棒值、轴向和径向功率分布等关键参数进行了细致评估。与蒙特卡洛代码 MCS 相比,A-SANM 的偏差为 -97 pcm。轴向和径向功率的差异分别为 ± 4 % 和 ± 3 %。此外,与 MCS 相比,杆值偏差为-6 pcm。总之,这项研究有效地阐明了多组 A-SANM 在高温气冷堆评估中的潜力和精确性。
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Development and verification of multigroup advanced semi analytic nodal method solver for HTGR analysis with MHTGR-350

This study introduces the multigroup advanced semi-analytic nodal method (A-SANM) tailored for the high-temperature gas-cooled reactor (HTGR) analysis. The A-SANM has been crafted specifically for reactors with hexagonal geometries, such as the Vodo-Vodyanoi energetichesky reactor (VVER) and HTGR. A triangular node was constructed with a 12-term basis to delineate the flux by integrating both the polynomial and hyperbolic functions. The multigroup calculation kernel of this approach was embedded in the nodal diffusion code, RAST-V. To evaluate the computational efficiency of the A-SANM, we employed the MHTGR-350 benchmark. This benchmark, associated with a modular high-temperature gas-cooled reactor, was established by the OECD/NEA under the NGNP Project in 2021. In this study, we conducted the Phase I calculations to evaluate the performance of the neutronics code. Key parameters including the multiplication factor, rod worth, and axial and radial power distributions were meticulously assessed. When juxtaposed with the Monte Carlo code MCS, the A-SANM exhibited a deviation of –97 pcm. Differences in the axial and radial power were ± 4 and ± 3 %, respectively. Furthermore, the rod worth discrepancy was –6 pcm when set against the MCS. In summary, this study effectively elucidates the potential and precision of the multigroup A-SANM for the HTGR evaluations.

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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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