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Safeguard aspects of /sup 244/Cm as a multiplier in cylindrical hybrid blankets

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5539029
In this work, the neutron multiplication and breeding performance of /sup 244/Cm is analyzed in connection with a deuterium-tritium (D-T)-driven experimental hybrid blanket in cylindrical geometry within the research program AYMAN in order to simulate relatively realistic neutron spectra for future hybrid reactors. Results show that the /sup 244/Cm(n,..gamma..) reaction rate of 0.0148 per D-T fusion neutron corresponds to a production rate of 50 g//sup 245/Cm per year-MW(t) fusion chamber power by a load factor of 75%. A relatively small fusion driver with 100 MW(t) of power would lead to the production of approx. 5 kg /sup 245/Cm per year under similar spectral conditions, enough to provide fuel for up to 50 explosives per year. The raw material required for this process would be approx. 25 kg of /sup 244/Cm per year, which can be extracted from the inventory of minor actinides from 30 tons of heavy metal, after a burnup of 33 GWd/ton in a 1250-MW(e) pressurized water reactor plant, containing 30% conventional mixed-oxide fuel (U-Pu) and 70% uranium and plutonium recycling. These numbers demonstrate clearly the necessity of revising safeguarding regulations prior to the introduction of fusion reactors.
Research Organization:
King Saud Univ., Saudi Arabia
OSTI ID:
5539029
Report Number(s):
CONF-860610-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 52
Country of Publication:
United States
Language:
English