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dc.contributor.authorCANO OTT D.en_GB
dc.contributor.authorPLOMPEN ARJANen_GB
dc.contributor.authorRULLHUSEN PETERen_GB
dc.contributor.authorN_TOF COLLABORATION Theen_GB
dc.date.accessioned2010-02-25T17:13:23Z-
dc.date.available2007-01-23en_GB
dc.date.available2010-02-25T17:13:23Z-
dc.date.issued2006en_GB
dc.date.submitted2007-01-23en_GB
dc.identifier.citation2006 AIP Conference Proceedings - Capture Gamma-ray Spectrometry and Related Topics. vol. 819 p. 318-322en_GB
dc.identifier.urihttp://publications.jrc.ec.europa.eu/repository/handle/JRC36173-
dc.description.abstractAccurate 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.en_GB
dc.description.sponsorshipJRC.D.5-Neutron physicsen_GB
dc.format.mediumPrinteden_GB
dc.languageENGen_GB
dc.publisherAmerican Institute of Physicsen_GB
dc.relation.ispartofseriesJRC36173en_GB
dc.titleNeutron Capture Cross Section Measurements at n_TOF of 237Np, 240Pu and 243Am for the Transmutation of Nuclear Wasteen_GB
dc.typeArticles in periodicals and booksen_GB
JRC Directorate:Health, Consumers and Reference Materials

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