Analysis of the TREAT LEU Conceptual Design

Technical Report · Tue Mar 01 04:00:00 EST 2016

DOI:https://doi.org/10.2172/1245183· OSTI ID:1245183

Connaway, H. M. ^[1]; Kontogeorgakos, D. C. ^[1]; Papadias, D. D. ^[1]; Brunett, A. J. ^[1]; Mo, K. ^[1]; Strons, P. S. ^[1]; Fei, T. ^[1]; Wright, A. E. ^[1]

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

Analyses were performed to evaluate the performance of the low enriched uranium (LEU) conceptual design fuel for the conversion of the Transient Reactor Test Facility (TREAT) from its current highly enriched uranium (HEU) fuel. TREAT is an experimental nuclear reactor designed to produce high neutron flux transients for the testing of reactor fuels and other materials. TREAT is currently in non-operational standby, but is being restarted under the U.S. Department of Energy’s Resumption of Transient Testing Program. The conversion of TREAT is being pursued in keeping with the mission of the Department of Energy National Nuclear Security Administration’s Material Management and Minimization (M3) Reactor Conversion Program. The focus of this study was to demonstrate that the converted LEU core is capable of maintaining the performance of the existing HEU core, while continuing to operate safely. Neutronic and thermal hydraulic simulations have been performed to evaluate the performance of the LEU conceptual-design core under both steady-state and transient conditions, for both normal operation and reactivity insertion accident scenarios. In addition, ancillary safety analyses which were performed for previous LEU design concepts have been reviewed and updated as-needed, in order to evaluate if the converted LEU core will function safely with all existing facility systems. Simulations were also performed to evaluate the detailed behavior of the UO₂-graphite fuel, to support future fuel manufacturing decisions regarding particle size specifications. The results of these analyses will be used in conjunction with work being performed at Idaho National Laboratory and Los Alamos National Laboratory, in order to develop the Conceptual Design Report project deliverable.

• Research Organization: Argonne National Laboratory (ANL), Argonne, IL (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA) - Office of Defense Nuclear Nonproliferation - Office of Material Management and Minimization (M3)
• DOE Contract Number: AC02-06CH11357
• OSTI ID: 1245183
• Report Number(s): ANL/RTR/TM--16/1; 126340
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
CONVERSION
DESIGN
GRAPHITE
HIGHLY ENRICHED URANIUM
NEUTRON TRANSPORT THEORY
NUCLEAR FUELS
PERFORMANCE
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTOR CORES
SAFETY ANALYSIS
SIMULATION
SLIGHTLY ENRICHED URANIUM
STEADY-STATE CONDITIONS
THERMAL HYDRAULICS
TRANSIENTS
TREAT REACTOR
URANIUM DIOXIDE