EPJ Web of Conferences
Volume 42, 2013WONDER-2012 – 3rd International Workshop On Nuclear Data Evaluation for Reactor applications
|Number of page(s)
|Microscopic and Integral Nuclear data Measurements
|18 March 2013
Neutron transmission and capture of 241Am
1 CEA Saclay, Irfu/DSM/SPhN, Orme-des-Merisiers, 91191 Gif-sur-Yvette, France
2 EC-JRC-IRMM, Retieseweg 111, 2440 Geel, Belgium
3 CEA-Cadarache, DEN, 13108 Saint-Paul-les-Duranc, France
A set of neutron transmission and capture experiments based on the Time Of Flight (TOF) technique, were performed in order to determine the 241Am capture cross section in the energy range from 0.01 eV to 1 keV. The GELINA facility of the Institute for Reference Materials and Measurements (IRMM) served as the neutron source. A pair of C6D6 liquid scintillators was used to register the prompt gamma rays emerging from the americium sample, while a Li-glass detector was used in the transmission setup. Results from the capture and transmission data acquired are consistent with each other, but appear to be inconsistent with the evaluated data files. Resonance parameters have been derived for the data up to the energy of 100 eV.
© Owned by the authors, published by EDP Sciences, 2013
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