Review of microscopic integral cross section data in fundamental reactor dosimetry benchmark neutron fields
Conference
·
OSTI ID:7125504
The paper is intended to review and critically discuss microscopic integral cross section measurement and calculation data for fundamental reactor dosimetry benchmark neutron fields. Specifically the review covers the following fundamental benchmarks: (1) the spontaneous californium-252 fission neutron spectrum standard field; (2) the thermal-neutron induced uranium-235 fission neutron spectrum standard field; (3) the (secondary) intermediate-energy standard neutron field at the center of the Mol-..sigma sigma.., NISUS, and ITN--..sigma sigma.. facilities; (4) the reference neutron field at the center of the Coupled Fast Reactor Measurement Facility (CFRMF); (5) the reference neutron field at the center of the 10 percent enriched uranium metal, cylindrical, fast critical; and (6) the (primary) Intermediate-Energy Standard Neutron Field.
- Research Organization:
- Hanford Engineering Development Lab., Richland, Wash. (USA)
- DOE Contract Number:
- EY-76-C-14-2170
- OSTI ID:
- 7125504
- Report Number(s):
- HEDL-SA-1148(Draft); CONF-761127-5
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
BR-2 REACTOR
CALIFORNIUM 252
CALIFORNIUM ISOTOPES
CFRMF REACTOR
CROSS SECTIONS
DATA
DOSIMETRY
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
EVEN-EVEN NUCLEI
EVEN-ODD NUCLEI
EXPERIMENTAL REACTORS
FAST REACTORS
HEAVY NUCLEI
INFORMATION
IRRADIATION REACTORS
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
KINETICS
MATERIALS TESTING REACTORS
MINUTES LIVING RADIOISOTOPES
NEUTRON DOSIMETRY
NEUTRON FLUX
NEUTRON SOURCES
NEUTRON SPECTRA
NISUS FACILITY
NUCLEI
PARTICLE SOURCES
RADIATION FLUX
RADIATION SOURCES
RADIOISOTOPES
REACTOR KINETICS
REACTORS
RESEARCH AND TEST REACTORS
SPECTRA
TANK TYPE REACTORS
THERMAL REACTORS
URANIUM 235
URANIUM ISOTOPES
WATER COOLED REACTORS
WATER MODERATED REACTORS
YEARS LIVING RADIOISOTOPES
ZERO POWER REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
BR-2 REACTOR
CALIFORNIUM 252
CALIFORNIUM ISOTOPES
CFRMF REACTOR
CROSS SECTIONS
DATA
DOSIMETRY
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
EVEN-EVEN NUCLEI
EVEN-ODD NUCLEI
EXPERIMENTAL REACTORS
FAST REACTORS
HEAVY NUCLEI
INFORMATION
IRRADIATION REACTORS
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
KINETICS
MATERIALS TESTING REACTORS
MINUTES LIVING RADIOISOTOPES
NEUTRON DOSIMETRY
NEUTRON FLUX
NEUTRON SOURCES
NEUTRON SPECTRA
NISUS FACILITY
NUCLEI
PARTICLE SOURCES
RADIATION FLUX
RADIATION SOURCES
RADIOISOTOPES
REACTOR KINETICS
REACTORS
RESEARCH AND TEST REACTORS
SPECTRA
TANK TYPE REACTORS
THERMAL REACTORS
URANIUM 235
URANIUM ISOTOPES
WATER COOLED REACTORS
WATER MODERATED REACTORS
YEARS LIVING RADIOISOTOPES
ZERO POWER REACTORS