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http://dx.doi.org/10.7733/jnfcwt.2020.18.2.113

Options Study for the Neutralization of Elemental Sodium During the Pyroprocessing of Used Nuclear Fuel  

Westphal, Brian (Walsh Engineering Services)
Tolman, David (Idaho National Laboratory)
Tolman, Kevin (Idaho National Laboratory)
Frank, Steven (Idaho National Laboratory)
Herrmann, Steve (Idaho National Laboratory)
Warmann, Stephen (Idaho National Laboratory)
Marsden, Kenneth (Idaho National Laboratory)
Patterson, Michael (Idaho National Laboratory)
Publication Information
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT) / v.18, no.2, 2020 , pp. 113-118 More about this Journal
Abstract
An options study was performed for the treatment of residual elemental sodium in driver plenums following the chopping operation during the pyroprocessing of used nuclear fuel. Given the pending availability of a multi-function furnace for distillation and consolidation operations in the Fuel Conditioning Facility, the furnace was considered for the processing of driver plenums. Although two options (oxidation and distillation) could be performed in the multi-function furnace, neither option has been developed sufficiently to date to warrant the use of the furnace for treatment operations. Thus, it was decided to defer the treatment of elemental sodium from driver plenums in the multi-function furnace until more developed technologies and/or furnaces become available. In the interim, storage of the plenums and characterization efforts are recommended.
Keywords
EBR-II; Sodium; Pyroprocessing;
Citations & Related Records
Times Cited By KSCI : 2  (Citation Analysis)
연도 인용수 순위
1 DOE Record of Decision for the Treatment and Management of Sodium-Bonded Spent Nuclear Fuel, Federal Register, 65, 182 (2000).
2 C.E. Till and Y.I. Chang, Plentiful Energy: The Story of the Integral Fast Reactor, Createspace (2011).
3 M.F. Simpson and P. Bagri, "Basis for a Minimalistic Salt Treatment Approach for Pyroprocessing Commercial Nuclear Fuel," J. Nucl. Fuel Cycle Waste Technol., 16(1), 1-10 (2018).   DOI
4 B.R. Westphal, S.M. Frank, W.M. McCartin, D.G. Cummings, J.J. Giglio, T.P. O'Holleran, P.A. Hahn, T.S. Yoo, K.C. Marsden, K.J. Bateman, and M.N. Patterson, "Characterization of Irradiated Metal Waste from the Pyrometallurgical Treatment of Used EBR-II Fuel", Met. Trans. A, 46, 83-92 (2015).   DOI
5 R.G. Pahl, D.L. Porter, D.C. Crawford, and L.C. Walters, "Irradiation Behavior of Metallic Fast Reactor Fuels", J. Nucl. Mat., 188, 3-9 (1992).   DOI
6 D. Vaden, Sodium Removal and Disposal Handbook, Argonne National Laboratory Report ANL-87-30 (1987).
7 S. Herrmann et al., "Removal of Bond Sodium from an Irradiated Full-Length EBR-II Blanket Element via Melt-Drain-Evaporate Process", Proc. Global 2019, ANS, Seattle, WA (2019).