Status report on dosimetry benchmark neutron field development, characterization and application
Conference
·
OSTI ID:6596797
A brief but comprehensive review is presented of the status and future directions of benchmark neutron field development, characterization and application in perspective with two major objectives of reactor dosimetry: fuel fission rate and burn-up passive monitoring; and correlation of materials irradiation damage effects and projection to commercial power plants. The report focuses on the Light Water Reactor and Fast Breeder Reactor program needs. Current interfaces between dosimetry, reactor physics, cross section metrology solid state research and metallurgy are highlighted through a tentative classification of the benchmark field and its justification. A summary is given of indications drawn regarding the accuracy of fundamental fission cross sections, of dosimetry sensor nuclear data, of helium production assessment, of dosimetry fission yields, and of some other nuclear cross sections, on the basis of integral measurements in selected benchmark neutron fields. The ENDF/B IV data files are used as reference for the discussions.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- EY-76-C-14-2170
- OSTI ID:
- 6596797
- Report Number(s):
- HEDL-SA-1572; CONF-781002-2
- Country of Publication:
- United States
- Language:
- English
Similar Records
ENDF/B dosimetry cross section file benchmark neutron flux-spectral uncertainties
Review of microscopic integral cross section data in fundamental reactor dosimetry benchmark neutron fields
Review of microscopic integral cross section data in fundamental reactor dosimetry benchmark neutron fields
Conference
·
Wed Oct 01 00:00:00 EDT 1975
· Natl. Bur. Stand. (U.S.), Spec. Publ.; (United States)
·
OSTI ID:7365019
Review of microscopic integral cross section data in fundamental reactor dosimetry benchmark neutron fields
Conference
·
Wed Dec 31 23:00:00 EST 1975
·
OSTI ID:5297408
Review of microscopic integral cross section data in fundamental reactor dosimetry benchmark neutron fields
Conference
·
Fri Oct 01 00:00:00 EDT 1976
·
OSTI ID:7125504
Related Subjects
440101* -- Radiation Instrumentation-- General Detectors or Monitors & Radiometric Instruments
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY
ACTIVATION DETECTORS
BREEDER REACTORS
BWR TYPE REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FISSION CHAMBERS
FISSION FOIL DETECTORS
IONIZATION CHAMBERS
KINETICS
MEASURING INSTRUMENTS
NEUTRON DETECTORS
PERFORMANCE
PWR TYPE REACTORS
RADIATION DETECTORS
REACTOR INSTRUMENTATION
REACTOR KINETICS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY
ACTIVATION DETECTORS
BREEDER REACTORS
BWR TYPE REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FISSION CHAMBERS
FISSION FOIL DETECTORS
IONIZATION CHAMBERS
KINETICS
MEASURING INSTRUMENTS
NEUTRON DETECTORS
PERFORMANCE
PWR TYPE REACTORS
RADIATION DETECTORS
REACTOR INSTRUMENTATION
REACTOR KINETICS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS