Analyses for conversion of the Georgia Tech Research Reactor from HEU to LEU fuel

Conference · Sun Sep 27 00:00:00 EDT 1992

DOI:https://doi.org/10.2172/37603· OSTI ID:10105850

Matos, J. E. ^[1]; Mo, S. C. ^[1]; Woodruff, W. L. ^[1]

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1. Argonne National Lab. (ANL), Argonne, IL (United States)

The 5 MW Georgia Tech Research Reactor (GTRR) is a heterogeneous, heavy water moderated and cooled reactor, fueled with highly enriched uranium aluminum alloy fuel plates. The GTRR is required to convert to low enrichment (LEU) fuel in accordance with USNRC policy. Results of design and safety analyses performed by the RERTR Program at the Argonne National Laboratory for LEU conversion of the GTRR are summarized. Only those parameters which could change as a result of replacing the fuel are addressed. The performance of the reactor and all safety margins with LEU fuel are expected to be about the same as those with the current HEU fuel.

• Research Organization: Argonne National Lab. (ANL), Argonne, IL (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); USDOE Office of Arms Control and Nonproliferation (AN)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 10105850
• Report Number(s): ANL/EP/CP-77802; CONF-9209266-1; ON: DE93002929
• Resource Relation: Conference: 1992 International Meeting on Reduced Enrichment for Research and Test Reactors, Roskilde (Denmark), 27 Sep - 1 Oct 1992; Other Information: PBD: [1992]
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
GTRR REACTOR
NUCLEAR FUELS
HIGHLY ENRICHED URANIUM
SLIGHTLY ENRICHED URANIUM
SAFETY ANALYSIS
DESIGN
PERFORMANCE
MODIFICATIONS
PROLIFERATION
FUEL ELEMENTS
Nuclear Criticality Safety Program (NCSP)
Plutonium (Pu)
International Atomic Energy Agency (IAEA)
Failed Fuel Stabilization Canister (FFSC)
Fast Breeder Reactor
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