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Title: Transient Reactor Test Facility (TREAT) Low Enriched Uranium (LEU) Conversion Progress

Abstract

The National Nuclear Security Administration Office of Material Management and Minimization (NNSA M3) is working towards converting the Transient Reactor Test Facility (TREAT) located at the Idaho National Laboratory (INL) from its original high-enriched uranium (HEU) core to a low-enriched uranium (LEU) core. TREAT reactor operations were restarted in November of 2017 and data obtained from the initial testing will be used to validate the existing ANL reactor modeling. Fuel block development has progressed with the completion of 2 and 4 inch crack free surrogate fuel blocks. Alternative fabrication methods for the fuel blocks continue to be explored and are showing promising results. Additionally, cladding oxidation studies have been performed and analyzed to initiate the down selection of cladding material to be used for the TREAT LEU fuel elements. This paper describes the current status of the above mentioned activities, and discusses the anticipated path forward for the conversion program as it progresses toward a final fuel design and fuel fabrication process.

Authors:
 [1];  [1];  [1];  [2];  [3]
  1. Idaho National Laboratory
  2. LANL
  3. ANL
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
1484453
Report Number(s):
INL/CON-18-51919-Rev000
DOE Contract Number:  
AC07-05ID14517
Resource Type:
Conference
Resource Relation:
Conference: RERTR, Edinburgh, Scotland, 11/04/2018 - 11/07/2018
Country of Publication:
United States
Language:
English
Subject:
11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS; TREAT; LEU; Frabrication; Modeling & Analysis; Fuel Blocks; Cladding; Oxidation

Citation Formats

Hartman, H.T., Coryell, B.D., Shelton-Davis, C.V., Luther, E.P., and Connaway, H.M. Transient Reactor Test Facility (TREAT) Low Enriched Uranium (LEU) Conversion Progress. United States: N. p., 2018. Web.
Hartman, H.T., Coryell, B.D., Shelton-Davis, C.V., Luther, E.P., & Connaway, H.M. Transient Reactor Test Facility (TREAT) Low Enriched Uranium (LEU) Conversion Progress. United States.
Hartman, H.T., Coryell, B.D., Shelton-Davis, C.V., Luther, E.P., and Connaway, H.M. Thu . "Transient Reactor Test Facility (TREAT) Low Enriched Uranium (LEU) Conversion Progress". United States. https://www.osti.gov/servlets/purl/1484453.
@article{osti_1484453,
title = {Transient Reactor Test Facility (TREAT) Low Enriched Uranium (LEU) Conversion Progress},
author = {Hartman, H.T. and Coryell, B.D. and Shelton-Davis, C.V. and Luther, E.P. and Connaway, H.M.},
abstractNote = {The National Nuclear Security Administration Office of Material Management and Minimization (NNSA M3) is working towards converting the Transient Reactor Test Facility (TREAT) located at the Idaho National Laboratory (INL) from its original high-enriched uranium (HEU) core to a low-enriched uranium (LEU) core. TREAT reactor operations were restarted in November of 2017 and data obtained from the initial testing will be used to validate the existing ANL reactor modeling. Fuel block development has progressed with the completion of 2 and 4 inch crack free surrogate fuel blocks. Alternative fabrication methods for the fuel blocks continue to be explored and are showing promising results. Additionally, cladding oxidation studies have been performed and analyzed to initiate the down selection of cladding material to be used for the TREAT LEU fuel elements. This paper describes the current status of the above mentioned activities, and discusses the anticipated path forward for the conversion program as it progresses toward a final fuel design and fuel fabrication process.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2018},
month = {11}
}

Conference:
Other availability
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