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논문 기본 정보

자료유형
학술저널
저자정보
Beausoleil G. (Idaho National Laboratory) Capriotti L. (Idaho National Laboratory) Curnutt B. (Idaho National Laboratory) Fielding R. (Idaho National Laboratory) Hayes S. (Idaho National Laboratory) Wachs D. (Idaho National Laboratory)
저널정보
한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제54권 제11호
발행연도
2022.11
수록면
4,084 - 4,094 (11page)
DOI
10.1016/j.net.2022.07.008

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The Advanced Fuels Campaign Fission Accelerated Steady-state Test (FAST) at Idaho National Laboratory (INL) completed its first irradiation cycle within the Advanced Test Reactor (ATR). The test focused on the irradiation of alloy fuel forms for use in sodium fast reactors. The first cycle of FAST testing was completed and four rodlets were removed for the initial post irradiation examination (PIE). The rodlet design and irradiation conditions were evaluated using Monte Carlo N-Particle (MCNP) for as-run power history and COMSOL for temperature analysis. These rodlets include a set of low burnups (~2.5 % fissions per initial metal atoms [%FIMA]), control rodlets, and a helium-bonded annular rodlet (4.7 %FIMA). Nondestructive PIE has been completed and includes visual inspection, neutron radiography and gamma scanning of the FAST capsules and rodlets. Radiography confirmed the integrity of the experiments, revealed that the annulus in the annular fuel was filled at a modest burnup (4.7 %FIMA), and indicated potential slumping of the cooler rodlets at lower burnup. Precision gamma scanning indicated mostly usual fission product behavior, except for cesium in the He-bonded annular fuel. Future destructive PIE will be necessary to fully interpret the effects of accelerated irradiation on U-Zr metallic fuel behavior

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