15msco2冷却微堆设计与性能分析

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Yuandong Zhang , Ren Li , Bowen Zhang , Yiran Miao , Chao Guo , Genglei Xia , Minjun Peng
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引用次数: 0

摘要

超临界二氧化碳(SCO2)冷却反应堆利用临界点附近热物理特性的剧烈变化来实现高密度压缩机运行和低密度反应堆运行。这种独特的特性可以在适度的反应堆出口温度下提高热效率,同时提高经济可行性和运行安全性。此外,基于sco2的涡轮机械(例如涡轮机和压缩机)具有出色的紧凑性,有利于模块化设计和小型化潜力。这些综合优势使sco2冷却堆成为全球核工程研究的重点。本文介绍了一种15msco2冷却微堆(SCMR-15)的综合设计和性能评估。通过多物理场建模优化了核心结构,其中热工计算确定了基本尺寸,并使用OpenMC代码进行蒙特卡罗模拟,解析了中子特性和反应性控制机制。计算分析表明:(1)控制鼓系统提供足够的停机余量,超出安全要求;(2)关键性能指标,包括功率峰值因子、燃料颗粒最高温度和包层峰值温度,仍远低于设计阈值;(3)一贯的负温度反应性系数和负空隙系数保证了固有的安全特性。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Design and performance analysis of 15MWth SCO2-cooled micro reactor
Supercritical carbon dioxide (SCO2)-cooled reactors leverage the drastic variations in thermophysical properties near the critical point to achieve high-density compressor operation and low-density reactor operation. This unique characteristic enables enhanced thermal efficiency at moderate reactor outlet temperature while improving the economic viability and operational safety. Furthermore, SCO2-based turbomachinery (e.g., turbine and compressor) exhibits exceptional compactness, facilitating modular design and miniaturization potential. These combined advantages have positioned SCO2-cooled reactor as a prominent research focus in nuclear engineering worldwide. This study presents the comprehensive design and performance evaluation of a 15MWth SCO2-cooled Micro Reactor (SCMR-15). The core configuration was optimized through multiphysics modeling, where thermal-hydraulic calculations determined fundamental dimensions, and Monte Carlo simulations using OpenMC code resolved neutronics characteristics and reactivity control mechanisms. Computational analyses demonstrated: (1) The control drum system provides sufficient shutdown margin, exceeding safety requirements; (2) Key performance metrics, including power peaking factor, fuel pellet maximum temperature, and cladding peak temperature, remain well below design thresholds; (3) Inherent safety features are ensured by consistently negative temperature reactivity coefficients and void coefficients.
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来源期刊
Nuclear Engineering and Technology
Nuclear Engineering and Technology 工程技术-核科学技术
CiteScore
4.80
自引率
7.40%
发文量
431
审稿时长
3.5 months
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
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