EPJ Web of Conferences
Volume 106, 2016ISRD 15 – International Symposium on Reactor Dosimetry
|Number of page(s)||9|
|Section||Cross Sections, Nuclear Data and Uncertainties|
|Published online||03 February 2016|
Use of Neutron Benchmark Fields for the Validation of Dosimetry Cross Sections
Sandia National Laboratories*, Radiation Effects Sciences & Applications Department, Albuquerque, NM 87185-1146, USA
a Corresponding author: email@example.com
Published online: 3 February 2016
The evolution of validation metrics for dosimetry cross sections in neutron benchmark fields is explored. The strength of some of the metrics in providing validation evidence is examined by applying them to the 252Cf spontaneous fission standard neutron benchmark field, the 235U thermal neutron fission reference benchmark field, the ACRR pool-type reactor central cavity reference benchmark fields, and the SPR-III fast burst reactor central cavity. The IRDFF dosimetry cross section library is used in the validation study and observations are made on the amount of coverage provided to the library contents by validation data available in these benchmark fields.
© Owned by the authors, published by EDP Sciences, 2016
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 2.0, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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