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

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.
Authors:
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Publication Date:
OSTI Identifier:
1177616
Report Number(s):
INL/JOU--13-30021
Journal ID: ISSN 0029-5450; TRN: US1500053
DOE Contract Number:
DE-AC07-05ID14517
Resource Type:
Journal Article
Resource Relation:
Journal Name: Nuclear Technology; Journal Volume: 189; Journal Issue: 2
Publisher:
American Nuclear Society (ANS)
Research Org:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Org:
USDOE Office of Nuclear Energy (NE)
Country of Publication:
United States
Language:
English
Subject:
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