Electrorefining of un-irradiated and irradiated U-6 wt. % Zr metal fuel for deposition of uranium
Source abstract
Abstract
The present paper reports the data on electrorefining of un-irradiated and irradiated U-6 wt. % Zr (U-Zr) fuel carried out at 773 K in LiCl-KCl-UCl 3 electrolyte in an augmented hot cell facility. The electrorefining cell and electrode handling system were specially designed, fabricated, and installed inside the hot cell. Potentiostatic electrorefining was employed for the selective deposition of uranium. About 61 % and 36 % of initial uranium feed was deposited during the electrorefining of un-irradiated and irradiated U-Zr fuel respectively. Current efficiencies of about 96 % and 80 % were obtained for un-irradiated and irradiated runs respectively. No significant change in concentration of uranium in the electrolyte was observed before and after the electrorefining. The co-deposition of other fission products was negligible and zirconium content in the uranium product was found to be 3 mg/g of uranium.
Source: expertdata · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Molten salt chemistry and electrochemical processes · Nuclear Materials and Properties · Nuclear reactor physics and engineering
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (29)
Show source-provided references
1. The integral fast reactor10.13182/NT88-129 ↗
2. Development of pyroprocessing technology10.1016/0149-1970(96)00007-8 ↗
3. Chemical basis for pyrochemical reprocessing of nuclear fuel10.1021/ie00049a022 ↗
4. J.P. Ackerman, T.R. Johnson, Partition of actinides and fission products between metal and molten salt phases - Theory, measurement and application to IFR pyroprocess development, No. ANL/CMT/CP-79275; CONF-930905-4. Argonne National Lab (1993).
5. Fuger · 1983
6. Thermodynamic properties of halides, United States Department of the Interior, Bureau of Mines
7. The dendrite growth, morphology control and deposition properties of uranium electrorefining10.1016/j.jnucmat.2021.153110 ↗
8. Actinides recovery from irradiated metallic fuel in LiCl–KCl melts10.1016/j.jnucmat.2015.08.045 ↗
9. Zr-rich layers electrodeposited onto stainless steel cladding during the electrorefining of EBR-II fuel10.1016/S0022-3115(99)00011-2 ↗
10. Zirconium behaviour during electrorefining of actinide-zirconium alloy in molten LiCl-KCl on aluminium cathodes10.1016/j.jnucmat.2016.01.033 ↗
11. Electrorefining of U-Pu-Zr-alloy fuel onto solid aluminium cathodes in molten LiCl-KCl10.1524/ract.2008.1493 ↗
12. Electrorefining of metallic fuel with burn-up of ∼7 at% in a LiCl-KCl melt10.1080/00223131.2018.1500317 ↗
13. R.W. Benedict, J.R. Krsul, R.D. Mariani, K. Park, G.M. Teske, Small-scale irradiated fuel electrorefining, ANL/FC/CP-78576, Argonne National Laboratory (1993).
14. Pyrochemical processing activities in Idaho
15. Overview of CRIEPI pyroprocessing activities
16. Measurement of standard potentials of actinides (U, Np, Pu, Am) in LiCl-KCl eutectic salt and separation of actinides from rare earths by electrorefining
17. T. Koyama, Status of spent fuel treatment in Japan, Status and Trends of Spent Fuel Reprocessing, IAEA-TECDOC-1467, International Atomic Energy Agency (2005).
18. Electrorefining studies on uranium alloys
19. Electrorefining of uranium and plutonium - a literature review10.1016/0022-3115(92)90515-M ↗
20. Electrorefining of irradiated experimental metallic fuel at high lanthanides concentration in the LiCl–KCl electrolyte10.1016/j.jnucmat.2019.151743 ↗
21. Current status of pyrochemical reprocessing research in India10.13182/NT08-A3954 ↗
22. Development of pyrochemical reprocessing for spent metal fuels10.1016/j.egypro.2011.06.057 ↗
23. Commencement of engineering scale U metal electrorefining in PPRDF, IGC-Annual-Report (2022) 34–36.
24. S. Nedumaran, P. Venkatesh, M. Chandra, S. Ghosh, N. Samanta, G. Pakhui, G. Sreenivasan, S. Vandarkuzhali, B.P. Reddy, Electrorefining of U-Pu-Zr alloy in LiCl-KCl eutectic, PLUTONIUM-75, Kalpakkam India (2016).
25. A new method for preparing hydroxide-free alkali chloride melts10.1149/1.2427694 ↗
26. Experimental investigations and thermodynamic modelling of KCl-LiCl-UCl3 system10.1016/j.calphad.2013.11.001 ↗
27. Redox behaviour of moisture in LiCl-KCl eutectic melts: a cyclic voltammetry study10.1080/00295450.2020.1743101 ↗
28. W.E. Miller, Z. Tomczuk, Method for making a uranium chloride salt product, Patent No.: US 6,800,262B1, Date of Patent: Oct. 5 (2004).
29. Spent fuel reprocessing options, IAEA-TECDOC-1587 (2008).