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Behavior of actinides in the Integral Fast Reactor fuel cycle

Authors: Courtney, J. C.; Lineberry, M. J.;

Behavior of actinides in the Integral Fast Reactor fuel cycle

Abstract

The Integral Fast Reactor (IFR) under development by Argonne National Laboratory uses metallic fuels instead of ceramics. This allows electrorefining of spent fuels and presents opportunities for recycling minor actinide elements. Four minor actinides ({sup 237}Np, {sup 240}Pu, {sup 241}Am, and {sup 243}Am) determine the waste storage requirements of spent fuel from all types of fission reactors. These nuclides behave the same as uranium and other plutonium isotopes in electrorefining, so they can be recycled back to the reactor without elaborate chemical processing. An experiment has been designed to demonstrate the effectiveness of the high-energy neutron spectra of the IFR in consuming these four nuclides and plutonium. Eighteen sets of seven actinide and five light metal targets have been selected for ten day exposure in the Experimental Breeder Reactor-2 which serves as a prototype of the IFR. Post-irradiation analyses of the exposed targets by gamma, alpha, and mass spectroscopy are used to determine nuclear reaction-rates and neutron spectra. These experimental data increase the authors` confidence in their ability to predict reaction rates in candidate IFR designs using a variety of neutron transport and diffusion programs.

Country
United States
Related Organizations
Keywords

Ebr-2 Reactor, Experimental Data 210500, Radioactive Waste Storage, Technical Aspects, Breeding, 21 Specific Nuclear Reactors And Associated Plants, Safeguards, Plutonium 240, 052000, Burnup, Actinides, Waste Management, Nuclear Fuels, Fuel Cycle, 050800, Neptunium 237, Radioactive Waste Management, 12 Management Of Radioactive And Non-Radioactive Wastes From Nuclear Facilities, Nuclear Reaction Kinetics, Spent Fuels, Post-Irradiation Examination, Spent Fuel Storage, Spent Fuels Reprocessing, Ifr Reactor, And Physical Protection, Americium 243, 055001, Americium 241, 11 Nuclear Fuel Cycle And Fuel Materials, Nuclear Materials Management, Plutonium, Reprocessing, Power Reactors, 98 Nuclear Disarmament, Inventories

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selected citations
These citations are derived from selected sources.
This is an alternative to the "Influence" indicator, which also reflects the overall/total impact of an article in the research community at large, based on the underlying citation network (diachronically).
BIP!Citations provided by BIP!
popularity
This indicator reflects the "current" impact/attention (the "hype") of an article in the research community at large, based on the underlying citation network.
BIP!Popularity provided by BIP!
influence
This indicator reflects the overall/total impact of an article in the research community at large, based on the underlying citation network (diachronically).
BIP!Influence provided by BIP!
impulse
This indicator reflects the initial momentum of an article directly after its publication, based on the underlying citation network.
BIP!Impulse provided by BIP!
1
Average
Average
Average