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dc.contributor.authorChen, Franklin Fun Kunen_US
dc.contributor.authorGriffith, P. (Peter)en_US
dc.contributor.authorMcManamy, Thomas Josephen_US
dc.contributor.authorWas, Gary S. (Gary Steven), 1953-en_US
dc.contributor.otherMassachusetts Institute of Technology. Department of Nuclear Engineering. Fusion Technology Programen_US
dc.contributor.otherMassachusetts Institute of Technology. Department of Nuclear Engineeringen_US
dc.date.accessioned2014-09-12T23:53:53Z
dc.date.available2014-09-12T23:53:53Z
dc.date.issued1977en_US
dc.identifier.urihttp://hdl.handle.net/1721.1/89511
dc.descriptionStatement of responsibility on title-page reads: Franklin Chen, Peter Griffith, Thomas McManamy, and Gary Wasen_US
dc.description"May 1977."en_US
dc.description"This study is basically an integration and extension of a doctor's thesis by Franklin Chen and a master's thesis by Gary Was."en_US
dc.descriptionIncludes bibliographical references (leaves 244-248)en_US
dc.description.abstractThe objective of this study was to evaluate a new concept for a Tokamak type fusion reactor blanket. The design was based on using a packed bed of lithium aluminate as the breeding material with helium gas cooling. The unique aspect of the design was the assumption that small coolant leaks were inevitable and should not necessitate major maintenance. A modularized design was chosen with cylindrical breeder rods and graphite shim rods. Redundancy was provided by designing the blanket such that if a module failed it could be depressurized and its heat load shared by the neighboring operating modules. The thermal hydraulic analysis evolved analytical and computational methods for determining the temperature profiles of all components and the pumping power requirements. A computer program TRIPORT was developed to evaluate the tritium retention and transport. A one dimensional ANISN code was used to determine the breeding ratio for different configurations.!  The thermal hydraulic, neutronic and mechanical aspects of the Breeder Rod Shim Rod (BRSR) design were combined to determine a design window, that is the allowable range of system parameters. Unfortunately adequate breeding could not be demonstrated so that there was no open window. Basically the low breeding was caused by -he inherently poor breeding potential of LiAlO, combined with the additional structure required for failure mode operation. However, this conclusion is based on a specific design concept (BRSR) and further research in the area may prove more fruitful.en_US
dc.format.extentxxiii, 248 leavesen_US
dc.publisherCambridge, Mass. : Fusion Technology Program, Massachusetts Institute of Technology, 1977en_US
dc.relation.ispartofseriesMITNE ; no. 213en_US
dc.subject.lccTK9008.M41 N96 no.213en_US
dc.subject.lcshTokamaksen_US
dc.subject.lcshFusion reactorsen_US
dc.subject.lcshBreeder reactorsen_US
dc.subject.lcshNuclear fuel elementsen_US
dc.titleA Solid breeder tokamak blanket designed for failure mode operationen_US
dc.typeTechnical Reporten_US
dc.identifier.oclc04536019en_US


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