Title: Neutron Capture Cross Section Measurements at n_TOF of 237Np, 240Pu and 243Am for the Transmutation of Nuclear Waste
Citation: 2006 AIP Conference Proceedings - Capture Gamma-ray Spectrometry and Related Topics. vol. 819 p. 318-322
Publisher: American Institute of Physics
Publication Year: 2006
JRC N°: JRC36173
URI: http://publications.jrc.ec.europa.eu/repository/handle/JRC36173
Type: Articles in periodicals and books
Abstract: 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_TOF [1] 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_TOF facility, innovative Data Acquisition System based on flash ADCs and the use of a high performance BaF2 Total Absorption Calorimeter as a detection device.
JRC Directorate:Health, Consumers and Reference Materials

Files in This Item:
There are no files associated with this item.

Items in repository are protected by copyright, with all rights reserved, unless otherwise indicated.