Research on key technologies for <sup>252</sup> Cf production in the United States

252Cf is a high-intensity isotope neutron source with significant demand in scientific research, military development, and other fields. Currently, only the United States and Russia have the conditions for large-scale production. This article introduces the development process of252Cf production in the United States from three aspects: the construction of high flux reactors, the design and irradiation of irradiation targets, and the radiochemical separation process and simulation calculation of ultra-plutonium nuclide production. Analyzing the effects of neutron flux, energy spectrum, irradiation target nuclide composition, irradiation scheme, etc. on the production of252Cf, and combining with the American radiochemical separation process and production data, an accurate prediction method for252Cf production using transport burnup simulation calculation is introduced. This article can provide valuable reference for the production of252Cf by high flux reactor irradiation in China.

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Publication Details

Journal
IET conference proceedings.
Published
2024-12-01
DOI
https://doi.org/10.1049/icp.2024.4108
Primary Topic
Metallurgical Processes and Thermodynamics
Type
article
Field-Weighted Citation Impact
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article

Research on key technologies for 252 Cf production in the United States

Mingyu Wu, Zhenyu Zhang, Hongyi Yang
IET conference proceedings.
Metallurgical Processes and Thermodynamics
article

Research on key technologies for 252 Cf production in the United States

Mingyu Wu, Zhenyu Zhang, Hongyi Yang
article en

Abstract

252Cf is a high-intensity isotope neutron source with significant demand in scientific research, military development, and other fields. Currently, only the United States and Russia have the conditions for large-scale production. This article introduces the development process of252Cf production in the United States from three aspects: the construction of high flux reactors, the design and irradiation of irradiation targets, and the radiochemical separation process and simulation calculation of ultra-plutonium nuclide production. Analyzing the effects of neutron flux, energy spectrum, irradiation target nuclide composition, irradiation scheme, etc. on the production of252Cf, and combining with the American radiochemical separation process and production data, an accurate prediction method for252Cf production using transport burnup simulation calculation is introduced. This article can provide valuable reference for the production of252Cf by high flux reactor irradiation in China.

IET conference proceedings.Vol. 2024(20)
China Institute of Atomic Energy (CN)
Openalex Percentile: Top 76%
Metallurgical Processes and Thermodynamics
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