Review of microscopic integral cross section data in fundamental reactor dosimetry benchmark neutron fields

Conference · Thu Jan 01 04:00:00 EST 1976

OSTI ID:5297408

Fabry, A.; McElroy, W. N.; Kellogg, L. S.; Lippincott, E. P.; Grundl, J. A.; Gilliam, D. M.; Hansen, G. E.

This 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: the spontaneous californium-252 fission neutron spectrum standard field; the thermal-neutron induced uranium-235 fission neutron spectrum standard field; the (secondary) intermediate-energy standard neutron field at the center of the Mol-..sigma sigma.., NISUS, and ITN-..sigma sigma.. facilities; the reference neutron field at the center of the Coupled Fast Reactor Measurement Facility; the reference neutron field at the center of the 10% enriched uranium metal, cylindrical, fast critical; the (primary) Intermediate-Energy Standard Neutron Field.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA)
• DOE Contract Number: EY-76-C-14-2170
• OSTI ID: 5297408
• Report Number(s): HEDL-SA-1148(Rev.1); CONF-761160-2
• Country of Publication: United States
• Language: English

Related Subjects

652026* -- Nuclear Properties & Reactions
A=220 & above
Experimental-- Spontaneous & Induced Fission-- (-1987)
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
BARYON REACTIONS
CALIFORNIUM 252
CALIFORNIUM ISOTOPES
DOCUMENT TYPES
EVEN-EVEN NUCLEI
FISSION
HADRON REACTIONS
HEAVY NUCLEI
ISOTOPES
NEUTRON REACTIONS
NEUTRON SPECTRA
NUCLEAR REACTIONS
NUCLEI
NUCLEON REACTIONS
RADIOISOTOPES
REVIEWS
SPECTRA
SPONTANEOUS FISSION
STANDARDS
TARGETS
THERMAL FISSION
URANIUM 235 TARGET
YEARS LIVING RADIOISOTOPES