Thi Dung Nguyen , Duy Long Ta , Thanh Mai Vu , Shinichi Namizono , Huu Thuan Mai , Huu Quyet Nguyen , Nhu Viet Ha Pham
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This study focuses on performing neutronics benchmarking calculations of the proposed NuScale-like core using SCALE/KENO-VI, evaluating k-eff, control rod worths, and power distributions with ENDF/B-VII.1 continuous energy (CE) and 252-group libraries. The impact of ENDF/B-VII.0, VII.1, and VIII.0 libraries on neutronics results was also assessed using Serpent 2 (v2.1.31). Results show that SCALE/KENO-VI with ENDF/B-VII.1 CE and 252-group libraries aligns well with the reference, with discrepancies within 44 pcm for reactivity prediction and generally less than 2 % for power distribution, except for the all-rods-in scenario using the 252-group library, which shows a reactivity deviation of 139 pcm. In addition, Serpent 2 with ENDF/B-VIII.0 produced notable differences in the k-eff values compared to ENDF/B-VII.0 and VII.1. Consequently, this work provides valuable and significant neutronics reference data for the proposed NuScale-like core model. 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引用次数: 0
摘要
在欧洲原子能机构McSAFER项目下,使用来自Serpent 2 (v2.2)和核数据库ENDF/B-VII.1的蒙特卡罗解决方案,提出了一个类似nuscal核心的中子基准。该基准旨在促进轻水冷却小型模块化反应堆(LW-SMRs)中子计算中的代码对代码的比较,由于先进的技术、许可进展和商业可行性,全球对其部署的兴趣日益浓厚。这凸显了对高保真度分析的需求,以评估这些反应堆的设计、安全性和运行特征。本研究的重点是使用SCALE/KENO-VI对拟议的nuscale类核心进行中子基准计算,使用ENDF/B-VII评估k-eff、控制棒价值和功率分布。1个连续能量(CE)和252组库。ENDF/B-VII的影响。还使用Serpent 2 (v2.1.31)评估了0、VII.1和VIII.0文库对中子结果的影响。结果表明:SCALE/KENO-VI与ENDF/B-VII.1CE和252-group文库与参考文献吻合良好,反应性预测误差在44 pcm以内,功率分布误差一般小于2%,除了使用252-group文库的全棒插入场景,其反应性偏差为139 pcm。此外,蛇2与ENDF/B-VIII。与ENDF/B-VII相比,0产生了显著的k-eff值差异。1. i . i . i。因此,本工作为提出的类nuscal核模型提供了有价值和重要的中子参考数据。此外,这里使用SCALE/KENO-VI开发的nuscale类堆芯模型可以作为未来nuscale类堆和其他类似低堆设计的中子学和堆芯性能分析的基础。
Neutronics benchmark calculations of the NuScale-like SMR core using SCALE/KENO-VI
A neutronics benchmark for a NuScale-like core has been proposed under the Euratom McSAFER project using Monte Carlo solutions from Serpent 2 (v2.2) and the nuclear data library ENDF/B-VII.1. The benchmark aims to facilitate code-to-code comparisons in neutronics calculations for light-water cooled small modular reactors (LW-SMRs), driven by growing global interest in their deployment due to advanced technology, licensing progress, and commercial viability. This highlights the need for high-fidelity analyses to assess the design, safety, and operational features of these reactors. This study focuses on performing neutronics benchmarking calculations of the proposed NuScale-like core using SCALE/KENO-VI, evaluating k-eff, control rod worths, and power distributions with ENDF/B-VII.1 continuous energy (CE) and 252-group libraries. The impact of ENDF/B-VII.0, VII.1, and VIII.0 libraries on neutronics results was also assessed using Serpent 2 (v2.1.31). Results show that SCALE/KENO-VI with ENDF/B-VII.1 CE and 252-group libraries aligns well with the reference, with discrepancies within 44 pcm for reactivity prediction and generally less than 2 % for power distribution, except for the all-rods-in scenario using the 252-group library, which shows a reactivity deviation of 139 pcm. In addition, Serpent 2 with ENDF/B-VIII.0 produced notable differences in the k-eff values compared to ENDF/B-VII.0 and VII.1. Consequently, this work provides valuable and significant neutronics reference data for the proposed NuScale-like core model. Moreover, the NuScale-like core model developed here using SCALE/KENO-VI can serve as a basis for future neutronics and core performance analyses for NuScale-like reactors and other similar LW-SMR designs.
期刊介绍:
Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters.
NET covers all fields for peaceful utilization of nuclear energy and radiation as follows:
1) Reactor Physics
2) Thermal Hydraulics
3) Nuclear Safety
4) Nuclear I&C
5) Nuclear Physics, Fusion, and Laser Technology
6) Nuclear Fuel Cycle and Radioactive Waste Management
7) Nuclear Fuel and Reactor Materials
8) Radiation Application
9) Radiation Protection
10) Nuclear Structural Analysis and Plant Management & Maintenance
11) Nuclear Policy, Economics, and Human Resource Development