Title :
On the Combination of Delayed Neutron and Delayed Gamma Measurement Techniques for Nuclear Fuel and Its Application to Nuclear Data Uncertainty Reduction
Author :
Perret, Gregory ; Jordan, Kelly A.
Author_Institution :
Paul Scherrer Inst., Villigen, Switzerland
Abstract :
Novel techniques to measure induced fissions in spent fuel after re-irradiation at low power have been developed and tested at the Proteus zero-power research reactor. The two techniques are based on the detection of high energy gamma-rays emitted by short-lived fission products and delayed neutrons.
Keywords :
fission; fission reactor theory; fission research reactors; gamma-ray detection; neutron detection; nuclear materials safeguards; radioactive waste processing; 235U; 238U; 239Pu; MOX fuel; PROTEUS zero-power research reactor; UO2 fuel; delayed gamma measurement technique; delayed neutron measurement technique; fast extraction systems; fuel isotopic composition; high energy gamma-ray detection; induced fissions; nuclear data uncertainty reduction; nuclear fuel; plutonium content nondestructive assay; short-lived fission products; spent fuel characterisation; spent fuel safeguard applications; thermal fissions; total fission rate; Fission reactors; Isotopes; Measurement techniques; Measurement uncertainty; Neutrons; Nuclear fuels; Uncertainty; Delayed gamma; delayed neutron; integral experiments; nuclear data; research reactor;
Journal_Title :
Nuclear Science, IEEE Transactions on
DOI :
10.1109/TNS.2012.2215339
