Neutron-induced fission cross section measurements for uranium isotopes {sup 236}U and {sup 234}U at LANSCE

Journal Article · Fri Apr 19 04:00:00 EDT 2013 · AIP Conference Proceedings

DOI:https://doi.org/10.1063/1.4802391· OSTI ID:22117010

Laptev, A. B.; Tovesson, F. ^[1]; Hill, T. S. ^[2]

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1. Los Alamos National Laboratory, Los Alamos NM 87545 (United States)
2. Idaho National Laboratory, Idaho Falls ID 83415 (United States)

A well established program of neutron-induced fission cross section measurement at Los Alamos Neutron Science Center (LANSCE) is supporting the Fuel Cycle Research program (FC R and D). The incident neutron energy range spans from sub-thermal up to 200 MeV by combining two LANSCE facilities, the Lujan Center and the Weapons Neutron Research facility (WNR). The time-of-flight method is implemented to measure the incident neutron energy. A parallel-plate fission ionization chamber was used as a fission fragment detector. The event rate ratio between the investigated foil and a standard {sup 235}U foil is converted into a fission cross section ratio. In addition to previously measured data new measurements include {sup 236}U data which is being analyzed, and {sup 234}U data acquired in the 2011-2012 LANSCE run cycle. The new data complete the full suite of Uranium isotopes which were investigated with this experimental approach. Obtained data are presented in comparison with existing evaluations and previous data.

• OSTI ID: 22117010
• Journal Information: AIP Conference Proceedings, Journal Name: AIP Conference Proceedings Journal Issue: 1 Vol. 1525; ISSN APCPCS; ISSN 0094-243X
• Country of Publication: United States
• Language: English

Related Subjects

73 NUCLEAR PHYSICS AND RADIATION PHYSICS
COMPARATIVE EVALUATIONS
CROSS SECTIONS
ENERGY DEPENDENCE
FISSION
FISSION FRAGMENTS
IONIZATION CHAMBERS
LOS ALAMOS
MEV RANGE
NEUTRON REACTIONS
NUCLEAR FRAGMENTATION
TIME-OF-FLIGHT METHOD
URANIUM 234 TARGET
URANIUM 235
URANIUM 236 TARGET