Evaluation of the Enhanced LEU Fuel (ELF) Design for Conversion of the Advanced Test Reactor to a Low-Enrichment Fuel Cycle
Abstract
A conceptual low-enrichment uranium (LEU) fuel design has been developed for the Advanced Test Reactor (ATR) at Idaho National Laboratory. The ATR is currently fueled with a high-enrichment fuel but is slated to be converted to LEU under programs led by the National Nuclear Security Administration of the U.S. Department of Energy. A conceptual LEU fuel design, the Enhanced LEU Fuel (ELF), has been developed assuming power peaking control through the use of variable fuel meat thicknesses and no use of burnable poison. In initial work, this design was shown to satisfy performance requirements for ATR operation. Following these design calculations, a safety analysis process was initiated to demonstrate that the ELF design would successfully meet safety limits for postulated accident conditions. Those calculations, performed using RELAP5 and ATR-SINDA, require physics analysis to provide spatial power distributions and kinetics parameters for various core operations configurations. Finally, this article describes the findings of the physics analysis and provides predictions for the behavior of a LEU-fueled version of ATR, and compares these to calculations of the performance of the current high-enrichment uranium fuel.
- Authors:
-
- Idaho National Lab. (INL), Idaho Falls, ID (United States). Reactor Physics Design and Analysis
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Publication Date:
- Research Org.:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE)
- OSTI Identifier:
- 1471052
- Report Number(s):
- INL/JOU-17-40906-Rev000
Journal ID: ISSN 0029-5450
- Grant/Contract Number:
- AC07-05ID14517
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Nuclear Technology
- Additional Journal Information:
- Journal Volume: 201; Journal Issue: 3; Journal ID: ISSN 0029-5450
- Publisher:
- Taylor & Francis - formerly American Nuclear Society (ANS)
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; Advanced Test Reactor; low-enrichment uranium; conversion
Citation Formats
DeHart, Mark D., Karriem, Zain, and Pope, Michael A. Evaluation of the Enhanced LEU Fuel (ELF) Design for Conversion of the Advanced Test Reactor to a Low-Enrichment Fuel Cycle. United States: N. p., 2017.
Web. doi:10.1080/00295450.2017.1322451.
DeHart, Mark D., Karriem, Zain, & Pope, Michael A. Evaluation of the Enhanced LEU Fuel (ELF) Design for Conversion of the Advanced Test Reactor to a Low-Enrichment Fuel Cycle. United States. https://doi.org/10.1080/00295450.2017.1322451
DeHart, Mark D., Karriem, Zain, and Pope, Michael A. Thu .
"Evaluation of the Enhanced LEU Fuel (ELF) Design for Conversion of the Advanced Test Reactor to a Low-Enrichment Fuel Cycle". United States. https://doi.org/10.1080/00295450.2017.1322451. https://www.osti.gov/servlets/purl/1471052.
@article{osti_1471052,
title = {Evaluation of the Enhanced LEU Fuel (ELF) Design for Conversion of the Advanced Test Reactor to a Low-Enrichment Fuel Cycle},
author = {DeHart, Mark D. and Karriem, Zain and Pope, Michael A.},
abstractNote = {A conceptual low-enrichment uranium (LEU) fuel design has been developed for the Advanced Test Reactor (ATR) at Idaho National Laboratory. The ATR is currently fueled with a high-enrichment fuel but is slated to be converted to LEU under programs led by the National Nuclear Security Administration of the U.S. Department of Energy. A conceptual LEU fuel design, the Enhanced LEU Fuel (ELF), has been developed assuming power peaking control through the use of variable fuel meat thicknesses and no use of burnable poison. In initial work, this design was shown to satisfy performance requirements for ATR operation. Following these design calculations, a safety analysis process was initiated to demonstrate that the ELF design would successfully meet safety limits for postulated accident conditions. Those calculations, performed using RELAP5 and ATR-SINDA, require physics analysis to provide spatial power distributions and kinetics parameters for various core operations configurations. Finally, this article describes the findings of the physics analysis and provides predictions for the behavior of a LEU-fueled version of ATR, and compares these to calculations of the performance of the current high-enrichment uranium fuel.},
doi = {10.1080/00295450.2017.1322451},
journal = {Nuclear Technology},
number = 3,
volume = 201,
place = {United States},
year = {Thu Aug 31 00:00:00 EDT 2017},
month = {Thu Aug 31 00:00:00 EDT 2017}
}
Works referenced in this record:
Validation of the ATR-SINDA Fuel Plate Model Using Advanced Test Reactor Startup Data
journal, December 1994
- Polkinghorne, Steven T.
- Nuclear Technology, Vol. 108, Issue 3