Development of a (U,Zr)C-graphite pulsed reactor fuel element

Conference · Sat Jan 01 00:00:00 EST 1977

OSTI ID:7221008

Reuscher, J A; Karnes, C H; Marion, R H

A new core is being designed to improve the performance of the Annular Core Pulse Reactor (ACPR). This design utilizes a two region core with the inner region containing high enthalpy fuel elements around the 228 mm diameter central irradiation cavity. An outer core region of uranium-zirconium hydride fuel elements is placed around the high-enthalpy inner core region to provide an adequate negative temperature coefficient for the entire core. A program has been conducted to develop a high-enthalpy fuel element using a graphite matrix fuel containing (U-Zr)C solid solution particles. The program has successfully developed a (U, Zr) C-graphite fuel element with a high volumetric enthalpy which can be used in a water cooled pulse reactor. Extensive tests have demonstrated the feasibility and safety of the fuel element design.

• Research Organization: Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
• DOE Contract Number: EY-76-C-04-0789
• OSTI ID: 7221008
• Report Number(s): SAND-76-9311; CONF-770807-4; TRN: 77-014472
• Resource Relation: Conference: 4. international conference on structural mechanics in reactor technology, San Francisco, CA, USA, 15 Aug 1977
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ACPR REACTOR
FUEL ELEMENTS
DESIGN
REACTOR CORES
TESTING
ENRICHED URANIUM REACTORS
HOMOGENEOUS REACTORS
HYDRIDE MODERATED REACTORS
MIXED SPECTRUM REACTORS
PULSED REACTORS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SOLID HOMOGENEOUS REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors