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

Volume

59

Issue

6

fYear

2012

Firstpage

3166

Lastpage

3172

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;

fLanguage

English

Journal_Title

Nuclear Science, IEEE Transactions on

Publisher

ieee

ISSN

0018-9499

Type

jour

DOI

10.1109/TNS.2012.2215339

Filename

6308742