Neutron Capture Cross Section Measurements at n{sub T}OF of 237Np, 240Pu and 243Am for the Transmutation of Nuclear Waste

Journal Article · Mon Mar 13 00:00:00 EST 2006 · AIP Conference Proceedings

DOI:https://doi.org/10.1063/1.2187878· OSTI ID:20798309

Cano-Ott, D; Alvarez-Velarde, F; Embid-Segura, M; Gonzalez-Romero, E; Guerrero, C; Martinez, T; Villamarin, D; Vincente, M C ^[1]; Abbondanno, U; Fujii, K; Milazzo, P M; Moreau, C ^[2]; Aerts, G; Andriamonje, S; Berthoumieux, E; Dridi, W; Gunsing, F; Pancin, J; Perrot, L; Plukis, A ^[3]

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1. Centro de Investigaciones Energeticas Medioambientales y Technologicas, Madrid (Spain)
2. Istituto Nazionale di Fisica Nucleare, Trieste (Italy)
3. CEA/Saclay - DSM, Gif-sur-Yvette (France)

Accurate and reliable neutron capture cross section data for actinides are necessary for the proper design, safety regulation and precise performance assessment of transmutation devices such as Fast Critical Reactors or Accelerator Driven Systems. In particular, the neutron capture cross sections of 237Np, 240Pu and 243Am play a key role in the design and optimization of strategies for the Transmutation of Nuclear Waste. The listed cross sections have been measured in 2004 at n{sub T}OF with a high accuracy due to a combination of features unique in the world: high instantaneous neutron fluence and excellent energy resolution of the n{sub T}OF facility, innovative Data Acquisition System based on flash ADCs and the use of a high performance BaF2 Total Absorption Calorimeter as a detection device.

• OSTI ID: 20798309
• Journal Information: AIP Conference Proceedings, Vol. 819, Issue 1; Conference: 12. international symposium on capture gamma-ray spectroscopy and related topics, Notre Dame, IN (United States), 4-9 Sep 2005; Other Information: DOI: 10.1063/1.2187878; (c) 2006 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA); ISSN 0094-243X
• Country of Publication: United States
• Language: English

Related Subjects

73 NUCLEAR PHYSICS AND RADIATION PHYSICS
AMERICIUM 243
CAPTURE
CROSS SECTIONS
DATA ACQUISITION SYSTEMS
ENERGY RESOLUTION
NEPTUNIUM 237
NEUTRON FLUENCE
NEUTRON REACTIONS
NEUTRONS
OPTIMIZATION
PLUTONIUM 240
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTES
SAFETY
TIME-OF-FLIGHT METHOD
TRANSMUTATION