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2007•Unpublished venueOpen access

Measurement of continuous-energy neutron-incident neutron-production double-differential cross sections for Al up to several hundred MeV

Satoshi Noda, Takehito WATANABE, Nobuhiro Shigyo, Kenji Ishibashi, Daiki Satoh, Tetsuya K. Sato, T. Nakamura, Robert C. Haight

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Abstract

Neutron-production double-differential cross sections for aluminum were measured using continuousenergy neutron from spallation target at the WNR facility in LANSCE.Incident neutron beam was produced by 800 MeV linac.NE213 liquid organic scintillators were utilized to detect the emitted neutron from the sample.A fission ionization chamber was set to monitor incident neutron flux.Incident neutron energy was determined by the time-of-flight method between spallation source to neutron detectors.Emitted neutron energy was obtained by the energy deposited in the neutron detector.

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Neutron-production double-differential cross sections for aluminum were measured using continuousenergy neutron from spallation target at the WNR facility in LANSCE.Incident neutron beam was produced by 800 MeV linac.NE213 liquid organic scintillators were utilized to detect the emitted neutron from the sample.A fission ionization chamber was set to monitor incident neutron flux.Incident neutron energy was determined by the time-of-flight method between spallation source to neutron detectors.Emitted neutron energy was obtained by the energy deposited in the neutron detector.

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Available abstract

Neutron-production double-differential cross sections for aluminum were measured using continuousenergy neutron from spallation target at the WNR facility in LANSCE.Incident neutron beam was produced by 800 MeV linac.NE213 liquid organic scintillators were utilized to detect the emitted neutron from the sample.A fission ionization chamber was set to monitor incident neutron flux.Incident neutron energy was determined by the time-of-flight method between spallation source to neutron detectors.Emitted neutron energy was obtained by the energy deposited in the neutron detector.

Key concepts: Neutron, Neutron detection, Neutron cross section, Bonner sphere, Scintillator, Spallation Neutron Source, Neutron source, Neutron flux

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