Irradiation performance of a U-7Mo in Al-Si matrix dispersion full-size fuel plate assembly

Journal Article · Thu Nov 30 00:00:00 EST 2023 · Nuclear Engineering and Design

DOI:https://doi.org/10.1016/j.nucengdes.2023.112761· OSTI ID:2290361

Woolstenhulme, Nicolas E.  ^[1]; Robinson, Adam B.  ^[1]; Nielsen, Joseph W.  ^[1]; Choi, Yong Joon  ^[1]; Johnson, Thomas A. ^[1]; Yim, J. S. ^[2]; Tahk, Y. W. ^[2]; Park, J. M. ^[2]

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1. Idaho National Laboratory (INL), Idaho Falls, ID (United States)
2. Korean Atomic Energy Research Institute, Daejeon (Korea, Republic of)

The Korea Atomic Energy Research Institute (KAERI) is leading the Ki-Jang Research Reactor (KJRR) project with the intent to develop a new reactor for medical isotope production and other nuclear research purposes. The KJRR core is designed to use high density fuel system where uranium alloyed with 7 wt% molybdenum (U-7Mo) particles are dispersed in a matrix of aluminum alloyed with 5 wt% silicon (Al-5Si) and clad in aluminum alloy 6061 (Al-6061) to form fuel plates. KAERI developed a fabrication facility to construct KJRR fuel assemblies and partnered with the Idaho National Laboratory (INL) to irradiate a full-size fuel assembly, with 21 total fuel plates, in the Advanced Test Reactor (ATR). Irradiation testing and subsequent Post Irradiation Exam (PIE) campaigns were performed successfully over a multi-year project. Monte Carlo neutronic calculations, coupling with a depletion code, were performed based on ATR’s as-run power history which showed that the highest power plate (plate 20) reached 83.1 % end-of-life (EOL) local burnup based on initial ²³⁵U content. Additionally, finite element thermal modeling was performed based as-run power history which showed a beginning-of-life (BOL) peak local heat flux of 184 W/cm². No anomalous fuel performance was observed during the irradiation and target test conditions were achieved. PIE showed favorable performance of the fuel assembly regarding all important phenomena. This paper describes the KJRR fuel assembly irradiation conditions and PIE data to support the conclusion that it performed well, without evidence of unexpected or problematic fuel performance, within an irradiation test designed to bound the KJRR design environment.

• Research Organization: Idaho National Laboratory (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• Grant/Contract Number: AC07-05ID14517
• OSTI ID: 2290361
• Report Number(s): INL/JOU-23-71195-Rev000
• Journal Information: Nuclear Engineering and Design, Vol. 416; ISSN 0029-5493
• Publisher: Elsevier
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
KJRR
U-Mo
Material test reactors
Dispersion fuel
Irradiation testing
Post irradiation examination