Title: Measurement at n_TOF of the 237Np(n,gamma) and 240Pu(n,gamma) Cross Sections for the Transmutation of Nuclear Waste
Citation: 2006 Conference Proceedings of the American Nuclear Society's Topical Meeting on Reactor Physics vol. C031 p. 1-8
Publisher: American Nuclear Society
Publication Year: 2006
JRC N°: JRC36175
URI: http://publications.jrc.ec.europa.eu/repository/handle/JRC36175
Type: Articles in periodicals and books
Abstract: The final design, safety assessment and precise performance analysis of transmutation devices such as Accelerator Driven Systems (ADS) or Fast Critical Reactors, need accurate and reliable nuclear data. The cross sections of 237Np and 240Pu have been measured in 2004 at n_TOF with good accuracy due to a combination of features unique in the world: high instantaneous neutron fluence and excellent energy resolution of the n_TOF facility [1], 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

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