2024年春の年会

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VIII. 核不拡散・保障措置・核セキュリティ » 801-2 核不拡散・保障措置・核セキュリティ技術

[2F10-14] 核不拡散・核セキュリティ

2024年3月27日(水) 14:45 〜 16:10 F会場 (21号館3F 21-314)

座長:堀 雅人(JAEA)

14:45 〜 15:00

[2F10] Reducing the Proliferation Risk of Utilizing HALEU Fuel in Sodium-Cooled Fast Reactors

*Eva Morgan Lisowski1, Hiroshi Sagara1 (1. Tokyo Tech)

キーワード:HALEU, sodium-cooled fast reactor, proliferation resistance, material attractiveness

Sodium-cooled fast reactors (SFRs) are a strong potential candidate for future energy production. Construction of commercial-size demonstration SFRs utilizing high assay low-enriched uranium (HALEU) metal fuel enriched up to less than 20% is underway. However, these technologies have been highly criticized for their ability to efficiently produce weapons-grade plutonium and associated proliferation risks. To identify ways to decrease the proliferation risks of HALEU fuel, the material and facility attractiveness of SFR designs to nonpeaceful actors seeking to produce weapons-usable fissile material was analyzed, along with diversion scenario analysis. Finally, a comparative study between HALEU metal fuel, uranium-plutonium metal fuel, and fuel produced from re-enriched, reprocessed uranium was conducted.

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