Evaluated 182,183,184,186W Neutron Cross Sections and Covariances in the Resolved Resonance Region
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Oak Ridge National Laboratory (ORNL) has recently completed the resonance parameter evaluation of four tungsten isotopes, i.e., 182,183,184,186W, in the neutron energy range of thermal up to several keV. This nuclear data work was performed with support from the US Nuclear Criticality Safety Program (NCSP) in an effort to provide improved tungsten cross section and covariance data for criticality safety analyses. The evaluation methodology uses the Reich-Moore approximation of the R-matrix formalism of the code SAMMY to fit high-resolution measurements performed in 2010 and 2012 at the Geel linear accelerator facility (GELINA), as well as other experimental data sets on natural tungsten available in the EXFOR library. In the analyzed energy range, this work nearly doubles the resolved resonance region (RRR) present in the latest US nuclear data library ENDF/B-VII.1. In view of the interest in tungsten for distinct types of nuclear applications and the relatively homogeneous distribution of the isotopic tungsten—namely, 182W(26.5%), 183W(14.31%), 184W(30.64%), and 186W(28.43%) - the completion of these four evaluations represents a significant contribution to the improvement of the ENDF library. This paper presents an overview of the evaluated resonance parameters and related covariances for total and capture cross sections on the four tungsten isotopes.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA)
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 1234329
- Resource Relation:
- Conference: ICNC 2015, Charlotte, NC (United States), 17 Sep 2015
- Country of Publication:
- United States
- Language:
- English
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TUNGSTEN 186 TARGET
TUNGSTEN 182 TARGET
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TUNGSTEN 184 TARGET
TUNGSTEN 183
TUNGSTEN 184
TUNGSTEN 185
TUNGSTEN 187
GAMMA RADIATION
NEUTRON REACTIONS
KEV RANGE 01-10
TOTAL CROSS SECTIONS
R MATRIX
CROSS SECTIONS
EVALUATED DATA
NUCLEAR DATA COLLECTIONS
APPROXIMATIONS
DATA COVARIANCES
LIBRARIES
RESONANCE
CAPTURE
EV RANGE
MILLI EV RANGE