Measurement of Neutron Induced Fission of 235U, 233U and 245Cm with the FIC Detector at the CERN n_TOF Facility
Conference
·
OSTI ID:971571
- Laboratori Nazionali di Legnaro, Italy
- ORNL
A series of measurements of neutron induced fission cross section of various TRU isotopes have been performed at the CERN n{_}TOF spallation neutron facility, in the energy range from thermal to nearly 250 MeV. The experimental apparatus consists in a fast ionization chamber (FIC), used as a fission fragment detector with a high efficiency. Good discrimination between alphas and fission fragments can be obtained with a simple amplitude threshold. In order to allow the monitoring of the neutron beam and to extract the n{_}TOF neutron flux, the well known cross section of the {sup 235}U(n,f) reaction, considered as a fission standard, has been used. Preliminary results for the cross section are shown for some selected isotopes such as {sup 235}U, {sup 233}U and {sup 245}Cm in the energy range from 0.050 eV to about 2 MeV.
- Research Organization:
- Oak Ridge National Laboratory (ORNL)
- Sponsoring Organization:
- SC USDOE - Office of Science (SC)
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 971571
- Country of Publication:
- United States
- Language:
- English
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