Article
 

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

Public Deposited

Downloadable Content

Download PDF
https://ir.library.oregonstate.edu/concern/articles/sj1393067

Descriptions

Attribute NameValues
Creator
Abstract
  • The Advanced Test Reactor (ATR) is conducting scoping studies for the conversion of its fuel from a highly enriched uranium (HEU) composition to a low-enriched uranium (LEU) composition, through the Reduced Enrichment for Research and Test Reactors Program, within the Global Threat Reduction Initiative. 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 reactor physics scoping and feasibility analysis of TRIGA fuel within the current ATR fuel element envelope and compares it to the functional requirements delineated by the Naval Reactors Program, which includes > 4.8 x 10¹⁴ fissions/s·g⁻¹ of ²³⁵U in test positions, a fast–to–thermal neutron flux ratio that has a < 5% deviation from its current value, a desired steady cycle power within the corner lobes, and an operational cycle length of 56 days at 120 MW. Other design parameters outside those put forth by the Naval Reactors Program that are investigated herein include axial and radial power profiles, effective delayed neutron fraction, and mean neutron generation time. The result of this study demonstrates potential promise for implementation of TRIGA fuel in the ATR from a reactor physics perspective; discussion of observations and limitations are provided herein.
  • Keywords: Core design, Reactor physics, Advanced Test Reactor
  • Keywords: Core design, Reactor physics, Advanced Test Reactor
Resource Type
DOI
Date Available
Date Issued
Citation
  • Lyons, J. A., Marcum, W. R., Morrell, S., & DeHart, M. (2015). Reactor Physics Scoping and Characterization Study on Implementation of TRIGA Fuel in the Advanced Test Reactor. Nuclear Technology, 189(2), 202-217. doi:10.13182/NT14-33
Journal Title
Journal Volume
  • 189
Journal Issue/Number
  • 2
Rights Statement
Funding Statement (additional comments about funding)
  • The authors would like to thank the members of the Reactor Conversions program within the GTRI for their continued technical feedback and fiscal support.
Publisher
Peer Reviewed
Language
Replaces

Relationships

Parents:

This work has no parents.

Items