Progress on High Energy Delayed Gamma Spectroscopy for Direct Assay of Pu in Spent Fuel

Conference · Wed Aug 11 04:00:00 EDT 2010

OSTI ID:1004510

Campbell, Luke W; Smith, Leon E

The direct, nondestructive measurement of fissile and fissionable isotopes in spent fuel is not yet possible. Current methods which infer plutonium content through proxy measurements and confirmatory burnup calculations have relatively large uncertainty and do not satisfy the desire for a measurement that is independent of operator declarations. We are currently exploring the High Energy Delayed Gamma Spectroscopy (HEDGS) technique for direct, independent Pu measurement in light-water reactor fuels. HEDGS exploits the unique distribution of fission-product nuclei from each of the fissile isotopes. Fission is stimulated in the sample with a source of interrogating neutrons, and delayed gamma rays from the decay of the short-lived fission-product nuclei are measured. The measured gamma spectrum from the unknown sample is then fit with a linear combination of gamma spectra from pure U-235, Pu-239, and Pu-241, as deduced from the known fission-product yield curves and decay properties of the fission-product nuclei, to determine the original proportions of these fissile isotopes. In previous work, we performed preliminary modeling studies of HEDGS on idealized single fuel pins of various burnups. Here, we report progress on extending our GEANT-based modeling tools to efficiently model full pressurized water reactor (PWR) fuel assemblies using variance reduction techniques specific to the background emissions and induced signal, as appropriate. Predicted performance for a nominal HEDGS instrument design, is reported for the assay of U-235, Pu-239 and Pu-241 in spent fuel assemblies ranging from fresh to 60 GWd/MTU in burnup.

• Research Organization: Pacific Northwest National Laboratory (PNNL), Richland, WA (US)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC05-76RL01830
• OSTI ID: 1004510
• Report Number(s): PNNL-SA-73177
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BURNUP
DECAY
DESIGN
DISTRIBUTION
FISSION
FUEL ASSEMBLIES
FUEL PINS
GAMMA SPECTRA
GAMMA SPECTROSCOPY
NEUTRONS
NUCLEAR FUELS
NUCLEAR MATERIALS MANAGEMENT
NUCLEI
PERFORMANCE
PLUTONIUM
PWR TYPE REACTORS
SIMULATION
SPENT FUELS