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Thermal conductivity of large HTGR fuel rods

Johnson, W.R.
General Atomic Co., San Diego, Calif. (USA)1976

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[en] The thermal conductivities of six types of unirradiated prototype large HTGR fuel rods, representing the maximum and minimum fissile and fertile fuel loadings for a large HTGR core, have been measured in vacuum and in helium by a radial heat flow direct heating method at 950⁰ to 1250⁰C. Results are presented and discussed

Primary Subject

SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS (E3300)

Source

Jan 1976; v p; GA-LTR--9; Available from NTIS; Available from NTIS. $7.60.

Record Type

Report

Report Number

GA-A--12910A

Country of publication

United States

Descriptors (DEI)

DATA, FUEL RODS, HTGR TYPE REACTORS, PRESSURE DEPENDENCE, TEMPERATURE DEPENDENCE, THERMAL CONDUCTIVITY

Descriptors (DEC)

FUEL ELEMENTS, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, INFORMATION, PHYSICAL PROPERTIES, REACTOR COMPONENTS, REACTORS, THERMODYNAMIC PROPERTIES

Reference NumberReference Number

7273658

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