Neutron Capture Cross Section Measurements at n_TOF of 237Np, 240Pu and 243Am for the Transmutation of Nuclear Waste
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Tipus de documentText en actes de congrés
Data publicació2005
EditorAmerican Institute of Physics (AIP)
Condicions d'accésAccés restringit per política de l'editorial
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.
CitacióCalviño, F. [et al.]. Neutron Capture Cross Section Measurements at n_TOF of 237Np, 240Pu and 243Am for the Transmutation of Nuclear Waste. A: International Symposium on Capture Gamma-Ray Spectroscopy and Related Topics. "12 International Symposium on Capture Gamma-ray Spectroscopy and Related Topics". Notre Dame, Indiana: American Institute of Physics (AIP), 2005, p. 318-322.
ISBN0-7354-0313-9
Versió de l'editorhttp://scitation.aip.org/dbt/dbt.jsp?KEY=APCPCS&Volume=819&Issue=1
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Paper_cano_pp_318-322.pdf![]() | 1,193Mb | Accés restringit |
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