Comparison of experimental and calculated spectrum-averaged neutron cross sections for the IAEA international reactor dosimetry file (IRDF-82)

Journal Article · Thu Mar 31 23:00:00 EST 1983 · Nucl. Sci. Eng.; (United States)

OSTI ID:5502120

Cullen, D E; Kocherov, N P; McLaughlin, P M

Calculated spectrum-averaged cross sections are presented for all of the reactions in the International Reactor Dosimetry File (IRDF-82) using the ten benchmark neutron fields that were distributed with IRDF-82. Comparisons to experimentally measured spectrum-averaged cross sections are presented for the /sup 252/Cf and /sup 235/U thermal fission spectra. This comparison shows that the difference between the measured and calculated spectrum averages is still much larger than the experimentally quoted uncertainties. This indicates that more precise knowledge of these spectra and further evaluations are still needed.

• Research Organization: International Atomic Energy Agency Nuclear Data Section, A-1400 Vienna
• OSTI ID: 5502120
• Journal Information: Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 83:4; ISSN NSENA
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
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73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
BARYON REACTIONS
CALCULATION METHODS
CALIFORNIUM 252
CALIFORNIUM ISOTOPES
CROSS SECTIONS
DATA
DOSIMETRY
EVEN-EVEN NUCLEI
EVEN-ODD NUCLEI
EXPERIMENTAL DATA
FISSION
FISSION SPECTRA
HADRON REACTIONS
HEAVY NUCLEI
IAEA SAFEGUARDS
INFORMATION
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
MINUTES LIVING RADIOISOTOPES
NEUTRON DOSIMETRY
NEUTRON REACTIONS
NEUTRON SPECTRA
NUCLEAR REACTIONS
NUCLEI
NUCLEON REACTIONS
NUMERICAL DATA
RADIOISOTOPES
REACTOR SAFETY
SAFEGUARDS
SAFETY
SPECTRA
THERMAL FISSION
URANIUM 235
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES