氦氙冷却反应堆直接布雷顿循环系统的启动和加速瞬态特性初步分析

IF 3.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Haoyang Liao , Fulong Zhao , Hui Bao , Ruibo Lu , Sichao Tan , Puzhen Gao , Ruifeng Tian
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引用次数: 0

摘要

氦-氙冷却反应堆直接布雷顿循环系统重量轻、结构紧凑、简单,在小型核电站中具有良好的应用前景。反应堆系统的安全启动非常重要,因此设计了系统启动方案。此外,反应堆系统在运行过程中可能会受到外部加速度的影响。反应堆系统在受到加速度影响后能否正常安全运行及其影响特性尚不清楚。为了验证系统启动方案的可行性,探讨加速度影响特性,开发了系统分析程序,模拟系统启动瞬态运行工况和反应堆系统在加速度影响下的瞬态运行工况。在加速度影响特性的研究中,加速度有不同的周期、幅值、类型和方向,负载状态分为随系统输出功率变化的负载变化和恒定负载。结果表明,所设计的系统启动方案可以安全启动反应堆系统。当反应堆系统具备随系统输出功率变化的负载能力时,可以忽略加速度的影响。如果负载恒定,反应堆系统在受到加速度影响后无法保证持续稳定运行,存在失流事故(LOFA)风险。相关研究成果为反应堆系统启动方案设计和加速度对反应堆系统影响特性的研究提供了理论参考和支持。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Preliminary analysis of startup and acceleration transient characteristics of helium-xenon cooled reactor direct brayton cycle system
Helium-xenon cooled reactor direct Brayton cycle system has excellent application prospects in small nuclear power plants due to its light weight, high compactness and simple structure. The safe startup of reactor system is very important, so the system startup scheme is designed. In addition, reactor system may be affected by external acceleration during operation. Whether reactor system can operate normally and safely after being affected by acceleration and its influence characteristics are not clear. In order to verify the feasibility of the system startup scheme and explore the acceleration influence characteristics, the system analysis program was developed to simulate the system startup transient operating conditions and the transient operating conditions of reactor system under the influence of acceleration. In the research of acceleration influence characteristics, acceleration has different periods, amplitudes, types and directions, and the load state is divided into load change with system output power and constant load. The results show that the designed system startup scheme can start reactor system safely. Reactor system can ignore the influence of acceleration when it has load change with system output power ability. If the load remains constant, reactor system cannot ensure continuous and stable operation after being affected by acceleration, which has the risk of Loss of Flow Accident (LOFA). The relevant research results provide theoretical reference and support for the design of the reactor system startup scheme and the research on the influence characteristics of acceleration on reactor system.
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来源期刊
Progress in Nuclear Energy
Progress in Nuclear Energy 工程技术-核科学技术
CiteScore
5.30
自引率
14.80%
发文量
331
审稿时长
3.5 months
期刊介绍: Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.
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