Study of the IDGS technique for mixed plutonium-uranium (MOX) samples
- Tien K.
The isotope dilution gamma-ray spectrometry (IDGS) technique has been demonstrated for simultaneously measuring concentrations and isotopic compositions of plutonium in spent-fuel input dissolver solutions. For timely analyzing nuclear materials on the purpose of material accountancy and quality control/assurance, we have performed a feasibility study to implement the IDGS for measuring mixed plutonium-uranium oxide (MOX) samples at the Plutonium Fuel Center (PFC) of Japan Nuclear Cycle Development Institute (JNC). Proof-of-principle experiments and analysis have been conducted for developing simultaneous plutonium and uranium measurements in MOX samples with wide variation of Pu/U ratios including powder, pellets and process scraps from the MOX fuel fabrication plant at PFC. We have shown that FRAM can be used with the IDGS technique to simultaneously determine plutonium and uranium isotopic compositions and concentrations in MOX samples at PFC, JNC. The uncertainties of the results are somewhat large due to weak statistics. If better statistics are obtained by either using more plutonium in the measurements, acquire the data for longer time, or using higher efficiency detector then the results can be better. The accuracy of the results can also be improved by a factor of 2-3 by using the generalized IDGS technique instead of this traditional IDGS.
- Research Organization:
- Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
- Sponsoring Organization:
- USDOE
- OSTI ID:
- 977696
- Report Number(s):
- LA-UR-04-4191; TRN: US1003682
- Resource Relation:
- Conference: Submitted to: 45th Annual INMM Meeting, Orlando, FL, USA, July 18-22, 2004
- Country of Publication:
- United States
- Language:
- English
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