Spectral-average cross section validation in LR-0 reactor spectrum of {sup 55}Mn(n,2n), {sup 90}Zr(n,2n) and {sup 127}I(n,2n) reactions - 25362
Conference
·
OSTI ID:23055075
- Hlavni 130, Husinec-Rez (Czech Republic)
This article deals with the validation of spectral average cross-sections (SACS) of {sup 55}Mn(n,2n){sup 54}Mn, {sup 90}Zr(n,2n){sup 89}Zr and {sup 127}I(n,2n){sup 126}I reactions in well-defined LR-0 reactor spectrum. The measurement of SACS for selected reactions is of high interest because they are used for the practical reactor dosimetry and also for refinement of prompt fission neutron spectra of {sup 235}U in the region of higher energies. Various experiments for description of neutron field in reactor and detector characterization, which are necessary for validation, are described. The spectral average cross-sections are derived from Net Peak Areas of irradiated samples measured using a semiconductor high purity germanium detector. The spectral average cross section in {sup 235}U prompt fission neutron spectrum was experimentally determined to be 0.239 ± 0.015 mb for {sup 55}Mn, 1.209 ± 0.052 mb for {sup 127}I and 0.107 ± 0.005 mb for {sup 90}Zr. The obtained results were compared with MCNP6 calculations using ENDF/B-VII.0, ENDF/B-VII.1, JEFF-3.1, JEFF-3.2, JENDL-3.3, JENDL-4, ROSFOND-2010, CENDL-3.1 and IRDFF-1.05 nuclear data libraries. Notable discrepancies were found in {sup 90}Zr(n,2n){sup 89}Zr and {sup 127}I(n,2n){sup 126}I reactions. (authors)
- Research Organization:
- American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 23055075
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
61 RADIATION PROTECTION AND DOSIMETRY
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
CROSS SECTIONS
DOSIMETRY
FISSION NEUTRONS
GE SEMICONDUCTOR DETECTORS
IODINE 127
IRRADIATION
LR-0 REACTOR
NEUTRON SPECTRA
NUCLEAR DATA COLLECTIONS
SEMICONDUCTOR MATERIALS
URANIUM 235
VALIDATION
ZIRCONIUM 89
ZIRCONIUM 90
61 RADIATION PROTECTION AND DOSIMETRY
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
CROSS SECTIONS
DOSIMETRY
FISSION NEUTRONS
GE SEMICONDUCTOR DETECTORS
IODINE 127
IRRADIATION
LR-0 REACTOR
NEUTRON SPECTRA
NUCLEAR DATA COLLECTIONS
SEMICONDUCTOR MATERIALS
URANIUM 235
VALIDATION
ZIRCONIUM 89
ZIRCONIUM 90