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Effective Thermal Conductivity of Prismatic MHTGR Fuel

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Show simple item record Han, J. C. Driscoll, M. J. Todreas, N. E.
dc.contributor.other Advanced Nuclear Power Technology Program (Massachusetts Institute of Technology) en_US 2011-12-13T18:25:32Z 2011-12-13T18:25:32Z 1989-09-30
dc.description.abstract The Reactor Cavity Cooling System (RCCS) is an essential passive safety feature of the Modular High Temperature Gas-Cooled Reactor (MHTGR). Its function is to assure the protection of both public safety and owner investment. As shown schematically in Figure 1.1, the system relies upon all three of the classic modes of heat transfer: conduction through the graphic core dominates energy transport to the reactor vessel, from which radiation is the principal mechanism for heat transfer to the riser tubes, inside which natural convection transfers heat to ambient air which provides the ultimate heat sink. The latter two steps have been the subject of past and on-going analyses at MIT in the support of the MHTGR program, as document in references 1 through 10. In this report we focus attention on the in-vessel aspects of this sequence. en_US
dc.publisher Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program en_US
dc.relation.ispartofseries MIT-ANP;TR-005
dc.title Effective Thermal Conductivity of Prismatic MHTGR Fuel en_US
dc.type Technical Report en_US
dc.contributor.mitauthor Han, J. C.
dc.contributor.mitauthor Driscoll, M. J.
dc.contributor.mitauthor Todreas, N. E.
dspace.orderedauthors Han, J. C.; Driscoll, M. J.; Todreas, N. E. en_US

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