Neutronics and Transient Calculations for the Conversion of the Transient Reactor Rest Facility (TREAT)

Conference · Thu Jan 01 04:00:00 EST 2015

OSTI ID:1335502

Kontogeorgakos, Dimitrios C.; Connaway, Heather M.; Papadias, Dionissios D.; Wright, Arthur E.

The Transient Reactor Test Facility (TREAT) is a graphite-reflected, graphitemoderated, and air-cooled reactor fueled with 93.1% enriched UO2 particles dispersed in graphite, with a carbon-to-235U ratio of ~10000:1. TREAT was used to simulate accident conditions by subjecting fuel test samples placed at the center of the core to high energy transient pulses. The transient pulse production is based on the core’s selflimiting nature due to the negative reactivity feedback provided by the fuel graphite as the core temperature rises. The analysis of the conversion of TREAT to low enriched uranium (LEU) is currently underway. This paper presents the analytical methods used to calculate the transient performance of TREAT in terms of power pulse production and resulting peak core temperatures. The validation of the HEU neutronics TREAT model, the calculation of the temperature distribution and the temperature reactivity feedback as well as the number of fissions generated inside fuel test samples are discussed.

• Research Organization: Argonne National Laboratory (ANL)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA) - Office of Defense Nuclear Nonproliferation - Office of Material Management and Minimization (NA-23) Reactor Conversion Program
• DOE Contract Number: AC02-06CH11357
• OSTI ID: 1335502
• Country of Publication: United States
• Language: English