Measurements at n{sub T}OF of the Neutron Capture Cross Section of Minor Actinides Relevant to the Nuclear Waste Transmutation

Journal Article · Tue May 24 00:00:00 EDT 2005 · AIP Conference Proceedings

DOI:https://doi.org/10.1063/1.1945275· OSTI ID:20722453

Cano-Ott, D; Alvarez-Velarde, F; Embid-Segura, M; Gonzalez-Romero, E; Guerrero, C; Villamarin, D; Vincente, M C ^[1]; Abbondanno, U; Milazzo, P M; Moreau, C ^[2]; Aerts, G; Andriamonje, S; Berthoumieux, E; Dridi, W; Gunsing, F; Pancin, J; Perrot, L; Plukis, A ^[3]; Alvarez, H; Benlliure, J ^[4]

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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)
4. Universidade de Santiago de Compostela (Spain); and others

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 a strategy for the Nuclear Waste Transmutation. 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: 20722453
• Journal Information: AIP Conference Proceedings, Vol. 769, Issue 1; Conference: International conference on nuclear data for science and technology, Santa Fe, NM (United States), 26 Sep - 1 Oct 2004; Other Information: DOI: 10.1063/1.1945275; (c) 2005 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
12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ABSORPTION
ACCELERATOR DRIVEN TRANSMUTATION
AMERICIUM 243
ANALOG-TO-DIGITAL CONVERTERS
CAPTURE
CROSS SECTIONS
DATA ACQUISITION SYSTEMS
DESIGN
ENERGY RESOLUTION
FISSION
NEPTUNIUM 237
NEUTRON FLUENCE
NEUTRON REACTIONS
NEUTRONS
PERFORMANCE
PLUTONIUM 240
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTES