Published 2008 | Version v1
Book

The neutron capture cross sections of 237Np(n,γ) and 240Pu(n,γ) and its relevance in the transmutation of nuclear waste

Description

Neutron capture cross sections of actinides are of great relevance for the Transmutation of Nuclear Waste in Accelerator Driven Systems (ADS) and Generation-IV reactors. The neutron capture cross sections of 237Np and 240Pu in the range of 1 eV to 2 keV were measured at the n-TOF facility with a Total Absorption Calorimeter. The data have been analyzed with the SAMMY code. The corresponding covariance matrices have been generated. The final cross sections are presented and compared to the previously existing ones.The n-TOF 237Np σ(n,γ) is in agreement with the evaluated data files below 300 eV and its is lower by 10 to 15% up to 2 keV. This discrepancy with the evaluated data files is also observed in the capture cross section derived from the transmission measurements of Gressier et al. In the case of the 240Pu σ(n,γ), the n-TOF σ(n,γ) agrees within uncertainties with JENDL-3.3 and JEFF-3.1, except for a group of resonances around 800 eV. Endf/B-VII data are lower than n-TOF and the mentioned evaluations, with differences that increase with neutron energy up to 15-20 per cent

Part of:
Proceedings of the 2007 International Conference on Nuclear Data for Science and Technology - ND 2007

Additional details

Identifiers

Publishing Information

Publisher
EDP Sciences
Imprint Place
Les Ulis (France)
ISBN
978-2-7598-0090-2; 978-2-7598-0091-9
Imprint Title
Proceedings of the 2007 International Conference on Nuclear Data for Science and Technology - ND 2007
Imprint Pagination
1422 p.
Journal Page Range
p. 627-630

Conference

Title
2007 International Conference on Nuclear Data for Science and Technology - ND 2007
Dates
22-27 Apr 2007
Place
Nice (France)

Optional Information

Notes
17 refs.; Full text available on Internet at: http://dx.doi.org/10.1051/ndata:07496