Effect of new cross section evaluations on neutron spectrum determination

Author

Griffin, P.J. ; Kelly, J.G. ; Luera, T.F. ; VanDenburg, J.

Author_Institution

Sandia Nat. Labs., Albuquerque, NM, USA

Volume

39

Issue

6

fYear

1992

fDate

12/1/1992 12:00:00 AM

Firstpage

2078

Lastpage

2085

Abstract

Several neutron cross section libraries, such as ENDF/B-VI and IRDF-90, have been made available to the dosimetry community. Recommendations are made for the source selection of reaction cross sections that vary significantly among the libraries. In general, integral parameters from spectra obtained from unfold/adjustment codes using the cross sections will not significantly change. A 61-reaction compendium of dosimetry cross sections drawn from existing evaluations has been compiled for use at the Sandia National Laboratories Radiation Metrology Laboratory. This dosimetry library (SNLRML) is recommended for use in spectrum determination with unfold/adjustment methods

Keywords

collections of physical data; dosimetry; neutron spectra; neutron-nucleus reactions; nuclear engineering computing; physics computing; SNLRML; dosimetry cross sections; dosimetry library; integral parameters; neutron cross section libraries; neutron spectrum determination; reaction cross sections; source selection; unfold/adjustment codes; Assembly; Chemical elements; Dosimetry; Inductors; Laboratories; Libraries; Metrology; Neutrons; Sensor phenomena and characterization; Testing;

fLanguage

English

Journal_Title

Nuclear Science, IEEE Transactions on

Publisher

ieee

ISSN

0018-9499

Type

jour

DOI

10.1109/23.211406

Filename

211406