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An evaluation of the Nb-93(n,n prime )Nb-93m dosimeter reaction for ENDF/B-VI

Technical Report ·
DOI:https://doi.org/10.2172/5550144· OSTI ID:5550144
The Nb-93(n,n{prime})Nb-93m reaction plays an important role in nuclear energy applications. Because of its low threshold energy and relatively long half-life, it is a desirable reaction for long-term neutron fluence dosimetry in nuclear fission reactors. An evaluation of the differential cross section for this reaction was completed in 1985 by this laboratory as part of a comprehensive effort involving all neutron cross sections for niobium. The objective was to provide input for ENDF/B-VI. It was difficult to produce a reliable evaluation for this reaction in 1985 because the information available then was sparse and quite uncertain. In fact, that evaluation was based entirely on nuclear model calculations. The evaluated cross sections below 0.7 MeV were derived from calculations carried out in this laboratory, while the higher energy values were obtained from the work of Strohmaier and co-workers. In 1985 there was only one published experimental differential cross section value to consider for this reaction. Even the half-life of Nb-93m was in serious doubt. During the five years between the completion of the earlier evaluation and the finalization of ENDF/B-VI there have been some significant improvements and additions to the experimental database for this reaction. Also, new model calculations have been performed. Therefore, it was considered worthwhile to produce a new evaluation of Nb-93(n,n{prime})Nb-93m for ENDF/B-VI which would supplant the one that had been completed in 1985.
Research Organization:
Argonne National Lab., IL (USA)
Sponsoring Organization:
DOE/ER
DOE Contract Number:
W-31109-ENG-38
OSTI ID:
5550144
Report Number(s):
ANL/NDM-117; ON: DE91006042
Country of Publication:
United States
Language:
English