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Basis for a Minimalistic Salt Treatment Approach for Pyroprocessing Commercial Nuclear Fuel KCI 등재 SCOPUS

  • 언어ENG
  • URLhttps://db.koreascholar.com/Article/Detail/347707
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방사성폐기물학회지 (Journal of the Korean Radioactive Waste Society)
한국방사성폐기물학회 (Korean Radioactive Waste Society)
초록

A simplified flowsheet for pyroprocessing commercial spent fuel is proposed in which the only salt treatment step is actinide drawdown from electrorefiner salt. Actinide drawdown can be performed using a simple galvanic reduction process utilizing the reducing potential of gadolinium metal. Recent results of equilibrium reduction potentials for Gd, Ce, Nd, and La are summarized. A description of a recent experiment to demonstrate galvanic reduction with gadolinium is reviewed. Based on these experimental results and material balances of the flowsheet, this new variant of the pyroprocessing scheme is expected to meet the objectives of minimizing cost, maximizing processing rate, minimizing proliferation risk, and optimizing the utilization of geologic repository space.

목차
1. Introduction
 2. Fission Product Partitioning in Molten Salts
 3. Alternative Pyroprocessing Flowsheet
 4. Recent Developments in Actinide Drawdown
 5. Proliferation Resistance
 6. Further Development
 7. Conclusions
 Acknowledgments
 REFERENCES
저자
  • Michael F. Simpson(University of Utah, Department of Metallurgical Engineering) Corresponding Author
  • Prashant Bagri(University of Utah, Department of Metallurgical Engineering)