Application of the SAMINT methodology to the new cross section evaluations of ⁶³Cu and ⁶⁵Cu^∗

¹ Oak Ridge National Laboratory, Reactor and Nuclear Systems Division, Oak Ridge, TN, USA
² Institute for Radiological Protection and Nuclear Safety, Neutronics and Criticality Safety Assessment Department, Fontenay aux Roses, France

^a e-mail: sobesv@ornl.gov

Published online: 13 September 2017

Abstract

The SAMINT methodology allows coupling of differential and integral data evaluations in a continuous-energy framework. Prior to development of the SAMINT code, integral experimental data such as in the International Criticality Safety Benchmark Experiments Project remained a tool for validation of completed nuclear data evaluations. Now, SAMINT extracts information from integral benchmarks in the form of calculated sensitivity coefficients by Monte Carlo codes such as CE TSUNAMI-3D or MCNP6 and combines it with the results of experimental cross section measurements to produce an updated cross section evaluation utilizing information from both sets of data. The use of the generalized linear least squares methodology ensures that proper weight is given to both the differential and integral data. SAMINT is not intended to bias nuclear data toward specific integral experiments, but it should be used to supplement evaluation of differential experimental data. This work demonstrates the application of the SAMINT methodology to the new Oak Ridge National Laboratory (ORNL) evaluations of the resonance parameters for two isotopes of copper: ⁶³Cu and ⁶⁵Cu.