THE USE OF MOLTEN CALCIUM IN THE PROCESSING OF METALLIC FAST REACTOR FUELS. APPENDIX 1: THE DETERMINATION OF TANTALUM, LANTHANUM AND BARIUM IN URANIUM BY TRACER TECHNIQUE AND *gamma/ SPECTROSCOPY
Technical Report
·
OSTI ID:4039583
The behavior of Pu, U, and some fission products in a system where Pu-- U alloy is melted with Ca was examined. Pu, U, and the noble flssion products remained in the fuel alloy phase; the rare earth and the alkaline earth metals were extracted into the Ca. It is concluded that a process based on the use of molten Ca is feasible for the processing of metallic fuels from fast reactors provided that the melting point of the fuel is considerably less than 1000 deg C. The processing of metallic reactor fuels by molten Ca did not compare favorably with oxide slagging. Tracer technique and gamma spectroscopy methods for the determination of Ta, La, and Ba in U are presented. (auth)
- Research Organization:
- United Kingdom Atomic Energy Authority. Research Group. Atomic Energy Research Establishment, Harwell, Berks, England
- NSA Number:
- NSA-15-023562
- OSTI ID:
- 4039583
- Report Number(s):
- AERE-R-2949
- Country of Publication:
- United Kingdom
- Language:
- English
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