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Evaluation of the /sup 115/In(n,n)/sup 115m/In reaction for the ENDF/B-V dosimetry file

Technical Report ·
DOI:https://doi.org/10.2172/7122031· OSTI ID:7122031
An evaluation of the /sup 115/In(n,n')/sup 115m/In reaction for the ENDF/B-V Dosimetry File is presented. This evaluation is based entirely on reported experimental differential data. Several data sets were renormalized prior to the evaluation in order to take into account recent adjustments in corresponding standard cross sections and in other nuclear parameters used for derivation of cross sections. The present evaluation is compared with the corresponding ENDF/B-IV evaluation. The value of the spectrum-average cross section for the standard neutron field resulting from thermal-neutron fission of /sup 235/U has been computed for this reaction using cross section values from the present evaluation. This computed cross section compares favorably with the result of a recent evaluation of integral data.
Research Organization:
Argonne National Lab., IL (USA)
DOE Contract Number:
W-31109-ENG-38
OSTI ID:
7122031
Report Number(s):
ANL/NDM-26
Country of Publication:
United States
Language:
English