Inert matrix fuel neutronic, thermal-hydraulic, and transient behavior in a light water reactor

• Published in: Journal of nuclear materials 2006-06, Vol.352 (1-3), p.276-284
• Main Authors: Carmack, W.J., Todosow, M., Meyer, M.K., Pasamehmetoglu, K.O.
• Format: Article
• Language: English
• Subjects: ACTINIDES; CAPACITY; FAST REACTORS; FUEL CYCLE; FUEL ELEMENT CLUSTERS; inert matrix fuel; light water reactors; MATRIX MATERIALS; NUCLEAR FUEL CYCLE AND FUEL MATERIALS; NUCLEAR FUELS; POWER REACTORS; PROLIFERATION; SPENT FUELS; STORAGE; TESTING; TOXICITY; TRANSIENTS; WATER
• ISSN: 0022-3115; 1873-4820
• DOI: 10.1016/j.jnucmat.2006.02.098

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.