Transient thermal hydraulic analysis of a small passive lead–bismuth eutectic cooled fast reactor

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

Annals of Nuclear Energy Pub Date : 2024-08-29 DOI:10.1016/j.anucene.2024.110884

引用次数: 0

Abstract

The lead–bismuth eutectic cooled fast reactor (LFR) emerges as a cutting-edge technology in nuclear reactor design. This study introduces a compact, passive, and long-life LFR reactor LFR-180. The LFR-180 incorporates modular helical-coiled once-through steam generators (H-OTSG) and direct reactor auxiliary cooling systems. This integration enables the generation of superheated steam and passive safety features of the LFR-180, eliminating the necessity for a water-steam separation device and contributing to enhanced power generation efficiency. A detailed transient thermal hydraulic analysis is conducted with tailored models for LBE solidification and H-OTSG thermal hydraulics. Results demonstrate that LFR-180 is a fully passive reactor, requiring no intervention up to 149.1 h after shutdown. The H-OTSG can serve as the heat exchangers of the active safety systems that can effectively reduce the peak core outlet temperature from 1003.6 K under the SBO accident to 724.2 K after shutdown.

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小型被动式铅铋共晶冷却快堆的瞬态热水力分析

铅铋共晶冷却快堆（LFR）是核反应堆设计中的一项尖端技术。本研究介绍了一种结构紧凑、无源、长寿命的 LFR 反应堆 LFR-180。LFR-180 采用了模块化螺旋盘管直通式蒸汽发生器 (H-OTSG) 和直接反应堆辅助冷却系统。这种集成实现了过热蒸汽的产生和 LFR-180 的被动安全特性，消除了水-蒸汽分离装置的必要性，有助于提高发电效率。利用针对 LBE 凝固和 H-OTSG 热水力学量身定制的模型，进行了详细的瞬态热水力学分析。结果表明，LFR-180 是一个完全无源的反应堆，在停堆后 149.1 小时内无需干预。H-OTSG 可作为主动安全系统的热交换器，有效地将堆芯出口峰值温度从 SBO 事故下的 1003.6 K 降低到关堆后的 724.2 K。

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

Annals of Nuclear Energy 工程技术-核科学技术

CiteScore

4.30

自引率

21.10%

发文量

632

审稿时长

7.3 months

期刊介绍： Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.