GIFT-1.0: Advanced light water reactor fuel performance code

In response to emerging fuel technologies, such as Accident Tolerant Fuels (ATF), Small Modular Reactor (SMR) fuels, and extended spent fuel storage in the nuclear power industry, GIFT-1.0 was developed to enable full life-cycle simulations of Light Water Reactor (LWR) nuclear fuel, from steady-state operation to extended spent fuel storage. GIFT-1.0 is equipped with state-of-the-art models tailored to meet these new requirements. This paper introduces GIFT-1.0, presenting its structure, models, key features, validation, and performance. The code employs a high-fidelity 2-D axisymmetric (r, z) model for cladding mechanical analyses, allowing mechanistic modeling of multi-layered claddings, such as Cr-coated cladding and SiC cladding. GIFT-1.0 achieves highly accurate steady-state fuel behavior at affordable computational costs, making it suitable for full-core scale simulations.

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Publication Details

Journal
Nuclear Engineering and Technology
Published
2025-03-08
DOI
https://doi.org/10.1016/j.net.2025.103567
Citations
3
Primary Topic
Nuclear Materials and Properties
Type
article
Field-Weighted Citation Impact
1.55
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article

GIFT-1.0: Advanced light water reactor fuel performance code

Youho Lee, Chansoo Lee, Hyuntaek Rho, Kyuseok Shim et al.
3 citations
Nuclear Engineering and Technology
Nuclear Materials and Properties
1.55
article

GIFT-1.0: Advanced light water reactor fuel performance code

Youho Lee, Chansoo Lee, Hyuntaek Rho, Kyuseok Shim, Changhyun Jo
article en
3 citations

Abstract

In response to emerging fuel technologies, such as Accident Tolerant Fuels (ATF), Small Modular Reactor (SMR) fuels, and extended spent fuel storage in the nuclear power industry, GIFT-1.0 was developed to enable full life-cycle simulations of Light Water Reactor (LWR) nuclear fuel, from steady-state operation to extended spent fuel storage. GIFT-1.0 is equipped with state-of-the-art models tailored to meet these new requirements. This paper introduces GIFT-1.0, presenting its structure, models, key features, validation, and performance. The code employs a high-fidelity 2-D axisymmetric (r, z) model for cladding mechanical analyses, allowing mechanistic modeling of multi-layered claddings, such as Cr-coated cladding and SiC cladding. GIFT-1.0 achieves highly accurate steady-state fuel behavior at affordable computational costs, making it suitable for full-core scale simulations.

Nuclear Engineering and TechnologyVol. 57(9)
Seoul National University (KR)
Openalex Percentile: Top 19%
Nuclear Materials and Properties
1.55
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