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Title: Inert Matrix Fuel Neutronic, Thermal-Hydraulic, and Transient Behavior in a Light Water Reactor

Abstract

Currently, commercial power reactors in the United States operate on a once-through or open cycle, with the spent nuclear fuel eventually destined for long-term storage in a geologic repository. Since the fissile and transuranic (TRU) elements in the spent nuclear fuel present a proliferation risk, limit the repository capacity, and are the major contributors to the long-term toxicity and dose from the repository, methods and systems are needed to reduce the amount of TRU that will eventually require long-term storage. An option to achieve a reduction in the amount, and modify the isotopic composition of TRU requiring geological disposal is ‘burning’ the TRU in commercial light water reactors (LWRs) and/or fast reactors. Fuel forms under consideration for TRU destruction in light water reactors (LWRs) include mixed-oxide (MOX), advanced mixed-oxide, and inert matrix fuels. Fertile-free inert matrix fuel (IMF) has been proposed for use in many forms and studied by several researchers. IMF offers several advantages relative to MOX, principally it provides a means for reducing the TRU in the fuel cycle by burning the fissile isotopes and transmuting the minor actinides while producing no new TRU elements from fertile isotopes. This paper will present and discuss the results of amore » four-bundle, neutronic, thermal-hydraulic, and transient analyses of proposed inert matrix materials in comparison with the results of similar analyses for reference UOX fuel bundles. The results of this work are to be used for screening purposes to identify the general feasibility of utilizing specific inert matrix fuel compositions in existing and future light water reactors. Compositions identified as feasible using the results of these analyses still require further detailed neutronic, thermal-hydraulic, and transient analysis study coupled with rigorous experimental testing and qualification.« less

Authors:
; ; ;
Publication Date:
Research Org.:
Idaho National Laboratory (INL)
Sponsoring Org.:
DOE - NE
OSTI Identifier:
911745
Report Number(s):
INL/CON-05-00270
Journal ID: ISSN 0022-3115; TRN: US0800117
DOE Contract Number:  
DE-AC07-99ID-13727
Resource Type:
Conference
Resource Relation:
Journal Volume: 352; Journal Issue: 1-3; Conference: European Materials Research Society Symposium N - Nuclear Materials,Strasbourg, France,05/31/2005,06/03/2005
Country of Publication:
United States
Language:
English
Subject:
11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS; ACTINIDES; CAPACITY; FAST REACTORS; FUEL CYCLE; FUEL ELEMENT CLUSTERS; MATRIX MATERIALS; NUCLEAR FUELS; POWER REACTORS; PROLIFERATION; STORAGE; TESTING; TOXICITY; TRANSIENTS; WATER; SPENT FUELS; inert matrix fuel; light water reactors

Citation Formats

Carmack, Jon, Todoscow, Michael, Meyer, Mitchell K, and Pasamehmetoglu, Kemal O. Inert Matrix Fuel Neutronic, Thermal-Hydraulic, and Transient Behavior in a Light Water Reactor. United States: N. p., 2005. Web. doi:10.1016/j.jnucmat.2006.02.098.
Carmack, Jon, Todoscow, Michael, Meyer, Mitchell K, & Pasamehmetoglu, Kemal O. Inert Matrix Fuel Neutronic, Thermal-Hydraulic, and Transient Behavior in a Light Water Reactor. United States. https://doi.org/10.1016/j.jnucmat.2006.02.098
Carmack, Jon, Todoscow, Michael, Meyer, Mitchell K, and Pasamehmetoglu, Kemal O. Sun . "Inert Matrix Fuel Neutronic, Thermal-Hydraulic, and Transient Behavior in a Light Water Reactor". United States. https://doi.org/10.1016/j.jnucmat.2006.02.098. https://www.osti.gov/servlets/purl/911745.
@article{osti_911745,
title = {Inert Matrix Fuel Neutronic, Thermal-Hydraulic, and Transient Behavior in a Light Water Reactor},
author = {Carmack, Jon and Todoscow, Michael and Meyer, Mitchell K and Pasamehmetoglu, Kemal O},
abstractNote = {Currently, commercial power reactors in the United States operate on a once-through or open cycle, with the spent nuclear fuel eventually destined for long-term storage in a geologic repository. Since the fissile and transuranic (TRU) elements in the spent nuclear fuel present a proliferation risk, limit the repository capacity, and are the major contributors to the long-term toxicity and dose from the repository, methods and systems are needed to reduce the amount of TRU that will eventually require long-term storage. An option to achieve a reduction in the amount, and modify the isotopic composition of TRU requiring geological disposal is ‘burning’ the TRU in commercial light water reactors (LWRs) and/or fast reactors. Fuel forms under consideration for TRU destruction in light water reactors (LWRs) include mixed-oxide (MOX), advanced mixed-oxide, and inert matrix fuels. Fertile-free inert matrix fuel (IMF) has been proposed for use in many forms and studied by several researchers. IMF offers several advantages relative to MOX, principally it provides a means for reducing the TRU in the fuel cycle by burning the fissile isotopes and transmuting the minor actinides while producing no new TRU elements from fertile isotopes. This paper will present and discuss the results of a four-bundle, neutronic, thermal-hydraulic, and transient analyses of proposed inert matrix materials in comparison with the results of similar analyses for reference UOX fuel bundles. The results of this work are to be used for screening purposes to identify the general feasibility of utilizing specific inert matrix fuel compositions in existing and future light water reactors. Compositions identified as feasible using the results of these analyses still require further detailed neutronic, thermal-hydraulic, and transient analysis study coupled with rigorous experimental testing and qualification.},
doi = {10.1016/j.jnucmat.2006.02.098},
url = {https://www.osti.gov/biblio/911745}, journal = {},
issn = {0022-3115},
number = 1-3,
volume = 352,
place = {United States},
year = {2005},
month = {5}
}

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