一个小型模块化铅铋冷却快堆的静态自主负荷分析

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

Nuclear Engineering and Design Pub Date : 2025-05-14 DOI:10.1016/j.nucengdes.2025.114122

Kefan Zhang, Wenshun Duan, Weixiang Wang, Sifan Dong, Hongli Chen

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引用次数: 0

摘要

自本世纪以来，人们提出了自主负载跟随反应堆的概念，该概念允许核心功率通过固有的反应性反馈进行自我调整，而无需操作控制棒。结合其他特性，如可运输性和长寿命，这些将使小型模块化反应堆能够在小型电网应用中进行国际部署。本文提出并验证了适用于自动负荷跟踪分析的方法。在前人研制的小型模块化铅铋冷快堆的基础上，对利用朗肯循环的能量转换系统进行了优化，净效率达到34.8%。分析了自主负荷跟随的控制方法，将多种控制方法结合形成综合控制方案。结果表明，在自主负荷跟随条件下，系统的净输出功率可控制在100% ~ 0%之间。

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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Qusai-Static autonomous load following analysis of a small modular lead-bismuth cooled fast reactor

The concept of autonomous load following reactors, which allows the core power to adjust itself through inherent reactivity feedback without the operation of control rods, has been proposed since this century. When combined with other features such as transportability and long lifetime, these would enable the international deployment of small modular reactors for small grid applications. In this paper, the method suitable for autonomous load following analysis is developed and verified. Based on the small modular lead–bismuth cooled fast reactor developed in previous work, the energy conversion system using Rankine Cycle is optimized, and a net efficiency of 34.8% is achieved. The control methods of autonomous load following are analyzed and the comprehensive control scheme is formed by combing multiple control methods. The result suggests that the system’s net power output can be controlled between 100% and 0% under autonomous load following conditions.

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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.