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Fission Spectra of Minor Actinides

#0183-2


Measurements of the Fission Neutron Spectra of the Minor Actinides. Spontaneous Fission of Pu-240. 242 and Thermal Neutron Induced Fission of Cm-243, 245.

Tech Area / Field

  • FIR-NOT/Nuclear and Other Technical Data/Fission Reactors

Status
8 Project completed

Registration date
25.10.1995

Completion date
17.01.2000

Senior Project Manager
Nagai H

Leading Institute
Khlopin Radium Institute, Russia, St Petersburg

Collaborators

  • Technische Universität Dresden, Germany, Dresden\nForschungszentrum Karlsruhe Technik und Umwelt, Germany, Karlsruhe\nCEA / DRN, France, Paris\nBelgonucléaire, Belgium, Mol\nCOGEMA, France, Velizy\nJAERI, Japan, Tokyo\nENEA, Italy, Bologna

Project summary

Goal of the Project is to carry out the high accuracy measurements of energy spectra of neutrons emitted in the spontaneous fission of Pu-240, 242 and thermal neutron induced fission of Cm-243, 245.

The data on energy spectra and the number of neutrons in minor actinide fission are required to work out the transmutation conception using actinide burner reactors. These data are necessary in design process for calculation of the optimum reactor parameters, because the own neutron field of the spent fuel generated mainly by fission of these isotopes as well as the neutron fluxes resulting in the burning process must be taken into account in calculations.

The Project proposed is the second stage of the investigations of minor actinide fission neutron energy spectra started in the frame of Project #183. This second stage of the work includes the precise measurements of the spontaneous fission neutron spectra of Pu-240, 242 and the thermal neutron induced fission of Cm-243, Cm-245 in the energy range from 0.2 MeV to 12 MeV with the accuracy of 1–2%.

Technical Approach

The fission neutron spectra of nuclides will be measured by the time-of-flight method relative to the Cf-252 spontaneous fission neutron spectrum accepted as an international standard. Wide energy range neutron detectors will be used to register fission neutrons.

Expected Results

Accurate and reliable nuclear data on the spontaneous and induced fission neutron spectra of stated isotopes will be obtained, which are important for designing the Actinide Burner Reactors aimed at the efficient transmutation of minor actinides.

Role of Foreign Collaborators

The specialists from foreign collaborating institutions will take part in analyses and discussions of results of the measurements in the course of experiments. Critical review of the results and referee on the Project deliverables will be made by the specialists from JAERI.


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