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Neutron capture and fission cross sections of /sup 241/Pu. [0. 01 eV to 30 keV (ratio to 250 keV)]

Journal Article · · Nucl. Sci. Eng.; (United States)
OSTI ID:5106200
Neutron capture and fission cross sections of /sup 241/Pu were measured from 0.01 eV to 30 keV, and their ratio was measured up to 250 keV. The cross sections were normalized at thermal-neutron energies (0.02 to 0.03 eV) to the ENDF/B-IV evaluation. The source of pulsed neutrons was the Oak Ridge Electron Linear Accelerator. The gamma-ray detector used to detect capture and fission events was the ''total energy detector,'' which is a low-efficiency detector whose average efficiency is forced to be proportional to the energy of the interacting gamma rays by weighting these events according to their pulse height in the scintillator. Fast-neutron scintillation detectors with pulse-shape discrimination were used to detect fission events. The shape of the neutron flux was measured relative to the /sup 10/B(n,..cap alpha..) cross section. The measurements are unique for /sup 241/Pu in that absorption and fission were determined directly and simultaneously over a wide neutron energy range rather than indirectly by inferring capture from separate fission and total cross-section measurements. The results indicate that the neutron resonance region of the ENDF/B-IV evaluation underestimates capture by a factor of approximately 2. Above the resonance region (approximately 100 eV), there are no previous measurements of the differential capture cross section. These cross sections are important in plutonium-fueled reactors. 6 figures, 4 tables.
Research Organization:
Oak Ridge National Lab., TN
OSTI ID:
5106200
Journal Information:
Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 65:3; ISSN NSENA
Country of Publication:
United States
Language:
English