Full-core fuel analysis of a soluble boron-free SMR: Pellet-cladding interaction issue and enhancing fuel safety through loading pattern design

The full-core fuel behavior of the Soluble Boron-Free (SBF) Small Modular Reactor (SMR) was analyzed and compared with conventional pressurized water reactors (PWRs) and Soluble Boron-Using (SBU) SMRs to evaluate unique pellet-cladding interaction (PCI) risks. Unlike PWRs and SBU SMRs, SBF SMRs rely on control rods for reactivity control, leading to localized power increases during late-cycle withdrawal. This significantly elevates cladding hoop stress, particularly in fuel rods near control rods, increasing PCI risks even at moderate burnups. The maximum local cladding hoop stress due to PCI in SBF SMRs exceeds that of conventional PWRs, posing new fuel safety and qualification challenges despite being SMR fuel characteristics, such as lower power density, and extended relative fuel plenum length. Comparisons with boiling water reactors (BWRs) highlight the heightened PCI risk in SBF SMRs due to differences in core design and control strategies. A fuel loading strategy that positions high-burnup rods away from lead control rod banks effectively reduces peak cladding stress. However, PCI remains a concern, particularly for long-cycle cores with LEU+ fuel. These findings emphasize the need to integrate fuel performance considerations early in SBF SMR development to ensure safety, regulatory compliance, and adaptability for future LEU+ fuels.

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Publication Details

Journal
Nuclear Engineering and Technology
Published
2025-05-20
DOI
https://doi.org/10.1016/j.net.2025.103709
Citations
2
Primary Topic
Nuclear Materials and Properties
Type
article
Field-Weighted Citation Impact
1.04

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article

Full-core fuel analysis of a soluble boron-free SMR: Pellet-cladding interaction issue and enhancing fuel safety through loading pattern design

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2 citations
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article

Full-core fuel analysis of a soluble boron-free SMR: Pellet-cladding interaction issue and enhancing fuel safety through loading pattern design

Youho Lee, Chansoo Lee, Hyuntaek Rho, Jooil Yoon, Kyuseok Shim, Heejeong Jeong
article en
2 citations

Abstract

The full-core fuel behavior of the Soluble Boron-Free (SBF) Small Modular Reactor (SMR) was analyzed and compared with conventional pressurized water reactors (PWRs) and Soluble Boron-Using (SBU) SMRs to evaluate unique pellet-cladding interaction (PCI) risks. Unlike PWRs and SBU SMRs, SBF SMRs rely on control rods for reactivity control, leading to localized power increases during late-cycle withdrawal. This significantly elevates cladding hoop stress, particularly in fuel rods near control rods, increasing PCI risks even at moderate burnups. The maximum local cladding hoop stress due to PCI in SBF SMRs exceeds that of conventional PWRs, posing new fuel safety and qualification challenges despite being SMR fuel characteristics, such as lower power density, and extended relative fuel plenum length. Comparisons with boiling water reactors (BWRs) highlight the heightened PCI risk in SBF SMRs due to differences in core design and control strategies. A fuel loading strategy that positions high-burnup rods away from lead control rod banks effectively reduces peak cladding stress. However, PCI remains a concern, particularly for long-cycle cores with LEU+ fuel. These findings emphasize the need to integrate fuel performance considerations early in SBF SMR development to ensure safety, regulatory compliance, and adaptability for future LEU+ fuels.

Nuclear Engineering and TechnologyVol. 57(10)
Seoul National University (KR), Korea Atomic Energy Research Institute (KR), Korea Electric Power Corporation (South Korea) (KR)
National Research Foundation of Korea, Ministry of Science and ICT, South Korea, Korea Institute of Energy Technology Evaluation and Planning, Institute of Engineering Research, Seoul National University
Affordable and clean energy
Openalex Percentile: Top 25%
Nuclear Materials and Properties
1.04
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