On the combination of delayed neutron and delayed gamma techniques for fission rate measurement in nuclear fuel

Conference · Fri Jul 01 00:00:00 EDT 2011

DOI:https://doi.org/10.1109/ANIMMA.2011.6172907· OSTI ID:22039879

Perret, G; Jordan, K A ^[1]

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1. Paul Scherrer Institut, Villigen, 5232 (Switzerland)

Novel techniques to measure newly 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. The two techniques relate the measured signals to the total fission rate, the isotopic composition of the fuel, and nuclear data. They can be combined to derive better estimates on each of these parameters. This has potential for improvement in many areas. Spent fuel characterisation and safeguard applications can benefit from these techniques for non-destructive assay of plutonium content. Another application of choice is the reduction of uncertainties on nuclear data. As a first application of the combination of the delayed neutron and gamma measurement techniques, this paper shows how to reduce the uncertainties on the relative abundances of the longest delayed neutron group for thermal fissions in {sup 235}U, {sup 239}Pu and fast fissions in {sup 238}U. The proposed experiments are easily achievable in zero-power research reactors using fresh UO{sub 2} and MOX fuel and do not require fast extraction systems. The relative uncertainties (1{sigma}) on the relative abundances are expected to be reduced from 13% to 4%, 16% to 5%, and 38% to 12% for {sup 235}U, {sup 238}U and {sup 239}Pu, respectively. (authors)

• OSTI ID: 22039879
• Resource Relation: Conference: ANIMMA 2011: 2. International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications, Ghent (Belgium), 6-9 Jun 2011; Other Information: Country of input: France; 15 refs.; IEEE Catalog Number: CFP1124I-CDR
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ABUNDANCE
DELAYED GAMMA RADIATION
DELAYED NEUTRON ANALYSIS
DELAYED NEUTRONS
FAST FISSION
FISSION PRODUCTS
GAMMA DETECTION
ISOTOPE RATIO
MIXED OXIDE FUELS
NONDESTRUCTIVE ANALYSIS
PLUTONIUM 239
PROTEUS REACTOR
SAFEGUARDS
SPENT FUELS
THERMAL FISSION
URANIUM 235
URANIUM 238
URANIUM DIOXIDE