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An americium‐fueled gas core nuclear rocket

dc.contributor.authorKammash, Terry B.en_US
dc.contributor.authorGalbraith, David L.en_US
dc.contributor.authorJan, Ta‐Rongen_US
dc.date.accessioned2011-11-15T16:07:34Z
dc.date.available2011-11-15T16:07:34Z
dc.date.issued1993-01-10en_US
dc.identifier.citationKammash, 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.otherAPCPCS-271-1en_US
dc.identifier.urihttps://hdl.handle.net/2027.42/87734
dc.description.abstractA 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.publisherThe American Institute of Physicsen_US
dc.rights© The American Institute of Physicsen_US
dc.titleAn americium‐fueled gas core nuclear rocketen_US
dc.typeArticleen_US
dc.subject.hlbsecondlevelPhysicsen_US
dc.subject.hlbtoplevelScienceen_US
dc.description.peerreviewedPeer Revieweden_US
dc.contributor.affiliationumDepartment of Nuclear Engineering, The University of Michigan, Ann Arbor, Michigan 48109en_US
dc.description.bitstreamurlhttp://deepblue.lib.umich.edu/bitstream/2027.42/87734/2/585_1.pdf
dc.identifier.doi10.1063/1.43073en_US
dc.identifier.sourceProceedings of the tenth symposium on space nuclear power and propulsionen_US
dc.owningcollnamePhysics, Department of


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