1000-Mwe SGR. 90% ThO$sub 2$, 10% UO$sub 2$ ALTERNATE FUEL CORE THERMAL AND HYDRAULIC ANALYSIS | Zendy

J.K. Imig | Zendy

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1000-Mwe SGR. 90% ThO$sub 2$, 10% UO$sub 2$ ALTERNATE FUEL CORE THERMAL AND HYDRAULIC ANALYSIS

Author(s) -

J.K. Imig

Publication year - 1964

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/4005127

Subject(s) - core (optical fiber) , nuclear engineering , thermal hydraulics , thermal , materials science , analytical chemistry (journal) , nuclear reactor core , nuclear chemistry , radiochemistry , chemistry , physics , thermodynamics , composite material , engineering , heat transfer , chromatography

The thermal and hydraulic core parameters were determined using the SORTD I code for 90% ThO/sub 2/, 10% UO/sub 2/ fuel both for (1) a core containing 592 fuel elements corresponding to the UC reference core with a maximum UC temperature of 2000 deg F and (2) a core containing 784 fuel elements corresponding to a UC core with a maximum UC temperature of 1750 deg F. Eighteen rod elements with 2.5 in./sup 2/ and 3.5 in./sup 2/ fuel areas, and 30 rod elements with 4.5 in./sup 2/ and 5.5 in./sup 2/ fuel areas are analyzed for 8 cases. (auth

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