An americium‐fueled gas core nuclear rocket

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dc.contributor.author Kammash, Terry en_US
dc.contributor.author Galbraith, David L. en_US
dc.contributor.author Jan, Ta‐Rong en_US
dc.date.accessioned 2011-11-15T16:07:34Z
dc.date.available 2011-11-15T16:07:34Z
dc.date.issued 1993-01-10 en_US
dc.identifier.citation Kammash, Terry; Galbraith, David L.; Jan, Ta‐Rong (1993). "An americium‐fueled gas core nuclear rocket." AIP Conference Proceedings 271(1): 585-589. <http://hdl.handle.net/2027.42/87734> en_US
dc.identifier.other APCPCS-271-1 en_US
dc.identifier.uri http://hdl.handle.net/2027.42/87734
dc.description.abstract A gas core fission reactor that utilizes americium in place of uranium is examined for potential utilization as a nuclear rocket for space propulsion. The isomer 242mAm with a half life of 141 years is obtained from an (n, γ) capture reaction with 241Am, and has the highest known thermal fission cross section. We consider a 7500 MW reactor, whose propulsion characteristics with 235U have already been established, and re‐examine it using americium. We find that the same performance can be achieved at a comparable fuel density, and a radial size reduction (of both core and moderator/reflector) of about 70%. en_US
dc.publisher The American Institute of Physics en_US
dc.rights © The American Institute of Physics en_US
dc.title An americium‐fueled gas core nuclear rocket en_US
dc.subject.hlbsecondlevel Physics en_US
dc.subject.hlbtoplevel Science en_US
dc.description.peerreviewed Peer Reviewed en_US
dc.contributor.affiliationum Department of Nuclear Engineering, The University of Michigan, Ann Arbor, Michigan 48109 en_US
dc.description.bitstreamurl http://deepblue.lib.umich.edu/bitstream/2027.42/87734/2/585_1.pdf
dc.identifier.doi 10.1063/1.43073 en_US
dc.identifier.source Proceedings of the tenth symposium on space nuclear power and propulsion en_US
dc.owningcollname Physics, Department of
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