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Title: Fuel element design and analysis for potential LEU conversion of the Advanced Test Reactor

Abstract

This study provides a summary of the status of the design process for a low-enrichment replacement for the high-enrichment fuel that has historically been used in the Advanced Test Reactor (ATR) at Idaho National Laboratory. Under current long-term Department of Energy policy, the ATR will be converted to operate using low-enrichment fuel by 2030. To this end, an engineering evaluation and design process has been underway for more than ten years. Initially performed as a series of scoping studies for different design options, the last five years have seen a transition to a formal Safety-in-Design approach to the design and safety evaluation process. This paper focuses on such efforts in progress since 2012 to identify pre-conceptual and conceptual design candidates for ATR conversion. The Enhanced LEU Fuel (ELF) design is selected as the most promising conceptual design. Analyses and trade-off studies performed that led to that selection are described. Analysis of certain aspects of core performance for an ELF-fueled core relative to the current high-enrichment fuel show that only small and manageable changes to core operations will be necessary to support conversion of ATR to low-enrichment fuel.

Authors:
ORCiD logo [1];  [1];  [2]; ORCiD logo [3]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States). Reactor Physics Design and Analysis
  2. Idaho National Lab. (INL), Idaho Falls, ID (United States)
  3. Idaho National Lab. (INL), Idaho Falls, ID (United States). Reactor and Nuclear Safety Engineering
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Nonproliferation (NA-20); USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1473913
Alternate Identifier(s):
OSTI ID: 1549303
Report Number(s):
INL/JOU-17-41538-Rev000
Journal ID: ISSN 0149-1970
Grant/Contract Number:  
AC07-05ID14517; NA-212; DEAC07-05ID14517
Resource Type:
Accepted Manuscript
Journal Name:
Progress in Nuclear Energy
Additional Journal Information:
Journal Volume: 104; Journal ID: ISSN 0149-1970
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; ATR; LEU Conversion; ELF Mk 1A; Serpent

Citation Formats

DeHart, Mark D., Karriem, Zain, Pope, Michael A., and Johnson, Matthew P. Fuel element design and analysis for potential LEU conversion of the Advanced Test Reactor. United States: N. p., 2017. Web. doi:10.1016/j.pnucene.2017.09.007.
DeHart, Mark D., Karriem, Zain, Pope, Michael A., & Johnson, Matthew P. Fuel element design and analysis for potential LEU conversion of the Advanced Test Reactor. United States. doi:10.1016/j.pnucene.2017.09.007.
DeHart, Mark D., Karriem, Zain, Pope, Michael A., and Johnson, Matthew P. Fri . "Fuel element design and analysis for potential LEU conversion of the Advanced Test Reactor". United States. doi:10.1016/j.pnucene.2017.09.007. https://www.osti.gov/servlets/purl/1473913.
@article{osti_1473913,
title = {Fuel element design and analysis for potential LEU conversion of the Advanced Test Reactor},
author = {DeHart, Mark D. and Karriem, Zain and Pope, Michael A. and Johnson, Matthew P.},
abstractNote = {This study provides a summary of the status of the design process for a low-enrichment replacement for the high-enrichment fuel that has historically been used in the Advanced Test Reactor (ATR) at Idaho National Laboratory. Under current long-term Department of Energy policy, the ATR will be converted to operate using low-enrichment fuel by 2030. To this end, an engineering evaluation and design process has been underway for more than ten years. Initially performed as a series of scoping studies for different design options, the last five years have seen a transition to a formal Safety-in-Design approach to the design and safety evaluation process. This paper focuses on such efforts in progress since 2012 to identify pre-conceptual and conceptual design candidates for ATR conversion. The Enhanced LEU Fuel (ELF) design is selected as the most promising conceptual design. Analyses and trade-off studies performed that led to that selection are described. Analysis of certain aspects of core performance for an ELF-fueled core relative to the current high-enrichment fuel show that only small and manageable changes to core operations will be necessary to support conversion of ATR to low-enrichment fuel.},
doi = {10.1016/j.pnucene.2017.09.007},
journal = {Progress in Nuclear Energy},
number = ,
volume = 104,
place = {United States},
year = {2017},
month = {9}
}

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