Author
Larry J. Ott
Bio: Larry J. Ott is an academic researcher from Oak Ridge National Laboratory. The author has contributed to research in topics: Burnup & MOX fuel. The author has an hindex of 14, co-authored 44 publications receiving 1138 citations.
Papers
More filters
TL;DR: In this article, three general strategies for accident tolerant fuels are explored: modification of current state-of-the-art zirconium alloy cladding to further improve oxidation resistance (including use of coatings), replacement of Zr Alloy cladding with an alternative oxidation resistant high-performance cladding, and replacement of the monolithic ceramic oxide fuel with alternative fuel forms.
695 citations
TL;DR: In this paper, the impact of fuel/cladding materials on the fuel performance at normal operating conditions and on the reactor system under DB and BDB accident conditions was analyzed. But the authors focused on the impact on the nuclear power station's fuel performance.
209 citations
01 Jul 2012
TL;DR: In response to the accident at the Fukushima Daiichi nuclear power station in Japan, the U.S. Nuclear Regulatory Commission (NRC) and Department of Energy agreed to jointly sponsor an accident reconstruction study as a means of assessing severe accident modeling capability of the MELCOR code as mentioned in this paper.
Abstract: In response to the accident at the Fukushima Daiichi nuclear power station in Japan, the U.S. Nuclear Regulatory Commission (NRC) and Department of Energy agreed to jointly sponsor an accident reconstruction study as a means of assessing severe accident modeling capability of the MELCOR code. MELCOR is the state-of-the-art system-level severe accident analysis code used by the NRC to provide information for its decision-making process in this area. The objectives of the project were: (1) collect, verify, and document data on the accidents by developing an information portal system; (2) reconstruct the accident progressions using computer models and accident data; and (3) validate the MELCOR code and the Fukushima models, and suggest potential future data needs. Idaho National Laboratory (INL) developed an information portal for the Fukushima Daiichi accident information. Sandia National Laboratories (SNL) developed MELCOR 2.1 models of the Fukushima Daiichi Units 1, 2, and 3 reactors and the Unit 4 spent fuel pool. Oak Ridge National Laboratory (ORNL) developed a MELCOR 1.8.5 model of the Unit 3 reactor and a TRACE model of the Unit 4 spent fuel pool. The good correlation of the results from the SNL models with the data from the plants and with the ORNL model results provides additional confidence in the MELCOR code. The modeling effort has also provided insights into future data needs for both model development and validation.
82 citations
TL;DR: In this paper, the effect of variation in thermal conductivity of light water reactor fuel elements on core response during loss-of-coolant accident scenarios is examined, and sensitivity analyses to examine the effects of an increase in fuel thermal conductivities, up to 500%, on fuel temperature evolution during these transients are performed.
64 citations
TL;DR: In this paper, a study on the Fukushima Daiichi nuclear power station spent-fuel pool (SFP) at Unit 4 was presented, and the predicted SFP level and temperatures were in good agreement with measured data and are consistent with Tokyo Electric Power Company evaluation results.
Abstract: A study on the Fukushima Daiichi nuclear power station spent-fuel pool (SFP) at Unit 4 (SFP4) is presented in this paper. We discuss the design characteristics of SFP4 and its decay heat load in detail and provide a model that we developed to estimate the SFP evaporation rate based on the SFP temperature. The SFP level of SFP4 following the March 11, 2011, accident is predicted based on the fundamental conservation laws of mass and energy. Our predicted SFP level and temperatures are in good agreement with measured data and are consistent with Tokyo Electric Power Company evaluation results.
44 citations
Cited by
More filters
Journal Article•
28,685 citations
TL;DR: In this article, three general strategies for accident tolerant fuels are explored: modification of current state-of-the-art zirconium alloy cladding to further improve oxidation resistance (including use of coatings), replacement of Zr Alloy cladding with an alternative oxidation resistant high-performance cladding, and replacement of the monolithic ceramic oxide fuel with alternative fuel forms.
695 citations
TL;DR: A review of the development status for three accident tolerant fuel cladding technologies, namely coated zirconium-based cladding, ferritic alumina-forming alloy cladding and silicon carbide fiber-reinforced SCCM composite, is offered in this paper.
494 citations
TL;DR: In this article, an application of advanced oxidation-resistant iron alloys as light water reactor fuel cladding is proposed, based on specific limitations associated with zirconium alloys.
397 citations
TL;DR: In this paper, a set of model FeCrAl alloys containing 10−20Cr, 3−5Al, and 0−0.12Y in weight percent, were prepared by conventional arc-melting and hot-working processes to explore the effect of composition on the properties of FecrAlY alloys.
320 citations