Robust multipole approach for continuous nuclear Data: RKFIT implementation for X2 VVER-1000 reactor benchmark

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2024-11-15 DOI:10.1016/j.nucengdes.2024.113699

Abdolbaset Agh, Mahdi Zangian, Abdolhamid Minuchehr

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引用次数: 0

Abstract

The windowed multipole method stands out as a promising approach for effectively conducting on-the-fly Doppler-broadening for continuous nuclear cross-section data. Its implementation was predominantly relied on the conversion of the resolved resonance parameters and vector-fitting technique into the multipole representation. Recently, progress has been made in deriving multipole representations from continuous cross-section data, with one notable method being RKFIT mothed, that is a robust least square fitting method. The advantages and disadvantages of this method have been thoroughly investigated. Detailed instructions on utilizing this method are provided within the OpenMC Monte Carlo calculation code. The experimental reactor physics results of the X2 reactor (a VVER-1000 type reactor) have been used to benchmark the effectiveness of the continues nuclear data generated by this approach via the OpenMC code simulations. Also, the simulation results are compared with those obtained using continuous cross-section libraries and other multipole libraries.

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连续核数据的稳健多极方法：X2 VVER-1000 反应堆基准的 RKFIT 实施

带窗多极子方法是一种很有前途的方法，可以有效地对连续核截面数据进行即时多普勒扩频。其实施主要依赖于将解析的共振参数和矢量拟合技术转换为多极表示。最近，从连续横截面数据推导多极表示法取得了进展，其中一种值得注意的方法是 RKFIT mothed，这是一种稳健的最小平方拟合方法。对这种方法的优缺点进行了深入研究。OpenMC 蒙特卡罗计算代码中提供了使用这种方法的详细说明。X2 反应堆（VVER-1000 型反应堆）的反应堆物理实验结果被用来衡量这种方法通过 OpenMC 代码模拟生成的持续核数据的有效性。此外，还将模拟结果与使用连续截面库和其他多极库获得的结果进行了比较。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

Nuclear Engineering and Design 工程技术-核科学技术

CiteScore

3.40

自引率

11.80%

发文量

377

审稿时长

5 months

期刊介绍： Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.