Numerical and experimental study of shut-off rod assembly of a typical Indian research reactor under multi-support seismic excitation

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-02-01 DOI:10.1016/j.nucengdes.2025.113843

A.Ravi Kiran , M.K. Agrawal , S.K. Sinha

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引用次数: 0

Abstract

The Shut-off Rod (SoR) assembly is a critical safety-related system in the majority of nuclear reactors. For its seismic qualification, it is required to ensure that the Shut-off Rod falls freely through the guide tube in the stipulated time under seismic excitation. Due to this stringent requirement, full-scale testing is usually performed for seismic qualification. The present work demonstrates the methodology for the evaluation of functionality and integrity of SoR assembly under multi-support seismic excitation. Experimental and numerical studies are carried out on the SoR assembly of a typical Indian Research Reactor under multi-support seismic excitation. In the present work, the adequacy of numerical simulation for seismic qualification of the SoR assembly is explored. The present study provides two conditions to ensure the sufficiency of numerical simulation for the seismic qualification of the SoR assembly. The first condition is to ensure the structural integrity of the lattice guide tube and the second one is to ensure the free fall of the SoR. This paper provides a comprehensive overview of both experimental and numerical results, along with the sufficiency of numerical simulation for seismic qualification of the SoR assembly.

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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.