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
Similar Records
Neutron capture cross section of /sup 240/Pu. [200 eV to 350 keV]
Measurement of the neutron capture and fission cross sections of $sup 239$Pu and $sup 235$U, 0.02 eV to 200 keV, the neutron capture cross sections of $sup 197$Au, 10 to 50 keV, and neutron fission cross sections of $sup 233$U, 5 to 200 keV
Evaluation of the fission and capture cross sections of 240Pu; and 241Pu for ENDF/B-V. [10/sup -5/ eV to 20 MeV]
Journal Article
·
Wed Jun 01 00:00:00 EDT 1977
· Nucl. Sci. Eng.; (United States)
·
OSTI ID:7318967
Measurement of the neutron capture and fission cross sections of $sup 239$Pu and $sup 235$U, 0.02 eV to 200 keV, the neutron capture cross sections of $sup 197$Au, 10 to 50 keV, and neutron fission cross sections of $sup 233$U, 5 to 200 keV
Journal Article
·
Sat Jan 31 23:00:00 EST 1976
· Nucl. Sci. Eng., v. 59, no. 2, pp. 79-105
·
OSTI ID:4093952
Evaluation of the fission and capture cross sections of 240Pu; and 241Pu for ENDF/B-V. [10/sup -5/ eV to 20 MeV]
Conference
·
Sun Dec 31 23:00:00 EST 1978
·
OSTI ID:5696900
Related Subjects
652026* -- Nuclear Properties & Reactions
A=220 & above
Experimental-- Spontaneous & Induced Fission-- (-1987)
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BARYON REACTIONS
BARYONS
CAPTURE
COLD NEUTRONS
ELEMENTARY PARTICLES
ENERGY RANGE
EPITHERMAL NEUTRONS
EV RANGE
FAST NEUTRONS
FERMIONS
FISSION
HADRON REACTIONS
HADRONS
INTERMEDIATE NEUTRONS
KEV RANGE
MILLI EV RANGE
NEUTRON REACTIONS
NEUTRONS
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUCLEONS
PLUTONIUM 241 TARGET
RESONANCE NEUTRONS
TARGETS
THERMAL NEUTRONS
A=220 & above
Experimental-- Spontaneous & Induced Fission-- (-1987)
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BARYON REACTIONS
BARYONS
CAPTURE
COLD NEUTRONS
ELEMENTARY PARTICLES
ENERGY RANGE
EPITHERMAL NEUTRONS
EV RANGE
FAST NEUTRONS
FERMIONS
FISSION
HADRON REACTIONS
HADRONS
INTERMEDIATE NEUTRONS
KEV RANGE
MILLI EV RANGE
NEUTRON REACTIONS
NEUTRONS
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUCLEONS
PLUTONIUM 241 TARGET
RESONANCE NEUTRONS
TARGETS
THERMAL NEUTRONS