Reactor Physics Scoping and Characterization Study on Implementation of TRIGA Fuel in the Advanced Test Reactor

Journal Article · Wed Jan 01 00:00:00 EST 2014 · Nuclear Technology

DOI:https://doi.org/10.13182/NT14-33· OSTI ID:1177616

Lyons, Jennifer; Marcum, Wade R.; DeHart, Mark D.; Morrell, Sean R.

The Advanced Test Reactor (ATR), under the Reduced Enrichment for Research and Test Reactors (RERTR) Program and the Global Threat Reduction Initiative (GTRI), is conducting feasibility studies for the conversion of its fuel from a highly enriched uranium (HEU) composition to a low enriched uranium (LEU) composition. These studies have considered a wide variety of LEU plate-type fuels to replace the current HEU fuel. Continuing to investigate potential alternatives to the present HEU fuel form, this study presents a preliminary analysis of TRIGA® fuel within the current ATR fuel envelopes and compares it to the functional requirements delineated by the Naval Reactors Program, which includes: greater than 4.8E+14 fissions/s/g of ²³⁵U, a fast to thermal neutron flux ratio that is less than 5% deviation of its current value, a constant cycle power within the corner lobes, and an operational cycle length of 56 days at 120 MW. Other parameters outside those put forth by the Naval Reactors Program which are investigated herein include axial and radial power profiles, effective delayed neutron fraction, and mean neutron generation time.

• Research Organization: Idaho National Lab. (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: DE-AC07-05ID14517
• OSTI ID: 1177616
• Report Number(s): INL/JOU-13-30021; TRN: US1500053
• Journal Information: Nuclear Technology, Vol. 189, Issue 2; ISSN 0029-5450
• Publisher: American Nuclear Society (ANS)
• Country of Publication: United States
• Language: English

Related Subjects

98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
HIGHLY ENRICHED URANIUM
Slightly Enriched Uranium
Uranium Hydrides
Zirconium Hydrides
THERMAL NEUTRONS
ATR Reactor
TRIGA TYPE REACTORS
SHIP PROPULSION REACTORS
NUCLEAR FUELS
Specifications
REACTOR PHYSICS
URANIUM 235
COMPARATIVE EVALUATIONS
SOCIO-ECONOMIC FACTORS
DELAYED NEUTRON FRACTION
FEASIBILITY STUDIES
FUEL PLATES
Advanced Test Reactor
Low Enriched Uranium
TRIGA