Design characteristics of nuclear steam supply system and passive safety system for Innovative Small Modular Reactor (i-SMR)

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology Pub Date : 2025-05-12 DOI:10.1016/j.net.2025.103697

Sang Gyu Lim, Hyun Suk Nam, Do Hwan Lee, Sang Won Lee

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Abstract

In response to the growing global climate crisis, nuclear power, particularly through small modular reactors (SMRs), is emerging as a potential solution for sustainable energy production. This paper presents an innovative SMR (i-SMR) design being developed in the Republic of Korea, which integrates proven technologies from existing pressurized water reactors while emphasizing enhanced safety, cost-effectiveness, and operational flexibility. The i-SMR features a fully passive safety system, achieving a core damage frequency of 1E-9, thus significantly reducing the necessity for public evacuation during potential accidents. The i-SMR design incorporates several key elements, including a boron-free operation, a helical coil steam generator, an in-vessel control rod drive mechanism, and a canned-motor reactor coolant pump within an integrated nuclear steam supply system. This paper explores the design characteristics and the detailed operating mechanism of the passive safety system, comprising the passive emergency core cooling system, passive auxiliary feedwater system, and passive containment cooling system. Safety performance analyses were conducted for a loss-of-coolant accident using the Multi-dimensional Analysis of Reactor Safety (MARS) code. The analysis results demonstrate the performance and the thermal-hydraulic behavior of the passive safety system with key phenomena affecting the performance.

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新型小型模块化反应堆（i-SMR）核供汽系统及被动安全系统设计特点

为了应对日益严重的全球气候危机，核能，特别是通过小型模块化反应堆（smr），正在成为可持续能源生产的潜在解决方案。本文介绍了韩国正在开发的一种创新型SMR （i-SMR）设计，该设计集成了现有压水堆的成熟技术，同时强调了更高的安全性、成本效益和操作灵活性。i-SMR具有完全被动的安全系统，实现核心损坏频率为1E-9，因此在潜在事故期间显着减少公众疏散的必要性。i-SMR的设计包含了几个关键元素，包括无硼运行、螺旋线圈蒸汽发生器、容器内控制棒驱动机构，以及集成核蒸汽供应系统中的密封电机反应堆冷却剂泵。本文探讨了被动式安全系统的设计特点和具体运行机制，包括被动式应急堆芯冷却系统、被动式辅助给水系统和被动式安全壳冷却系统。采用反应堆安全多维分析（Multi-dimensional Analysis of Reactor Safety， MARS）规范对一起冷却剂损失事故进行了安全性能分析。分析结果显示了被动安全系统的性能和热液特性，并指出了影响系统性能的关键现象。

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

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