The Neutron Capture Cross Sections of 237NP(n,{gamma}) and 240Pu(n,{gamma}) and Its Relevance in the Transmutation of Nuclear Waste
Conference
·
OSTI ID:978772
- Centro de Investigaciones Energeticas Medioambientales y Technol., Madrid, Spain
- ORNL
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 {sup 237}Np and {sup 240}Pu 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.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE Office of Science (SC)
- DOE Contract Number:
- DE-AC05-00OR22725
- OSTI ID:
- 978772
- Resource Relation:
- Conference: International Conference on Nuclear Data for Science and Technology (ND2007), Nice, France, 20070422, 20070427
- Country of Publication:
- United States
- Language:
- English
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