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Walter, S |
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Wisshak, K |
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dc.date.accessioned |
2014-03-01T02:50:35Z |
|
dc.date.available |
2014-03-01T02:50:35Z |
|
dc.date.issued |
2006 |
en |
dc.identifier.issn |
0094243X |
en |
dc.identifier.uri |
https://dspace.lib.ntua.gr/xmlui/handle/123456789/35146 |
|
dc.subject |
237Np,240Pu and243Am, |
en |
dc.subject |
Neutron capture cross section |
en |
dc.subject |
Nuclear waste |
en |
dc.subject |
Total absorption calorimeter |
en |
dc.subject |
Transmutation |
en |
dc.title |
Neutron capture cross section measurements at n_TOF of237Np,240Pu and243Am for the transmutation of nuclear waste |
en |
heal.type |
conferenceItem |
en |
heal.identifier.primary |
10.1063/1.2187878 |
en |
heal.identifier.secondary |
http://dx.doi.org/10.1063/1.2187878 |
en |
heal.publicationDate |
2006 |
en |
heal.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 of237Np,240Pu and243Am 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 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. © 2006 American Institute of Physics. |
en |
heal.journalName |
AIP Conference Proceedings |
en |
dc.identifier.doi |
10.1063/1.2187878 |
en |
dc.identifier.volume |
819 |
en |
dc.identifier.spage |
318 |
en |
dc.identifier.epage |
322 |
en |