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Your search keyword '"Hajime Sekino"' showing total 2 results
Start Over Author "Hajime Sekino" Journal nuclear technology
2 results on '"Hajime Sekino"'

1. Irradiation Experiment on ZrC-Coated Fuel Particles for High-Temperature Gas-Cooled Reactors

Author

Hajime Sekino, Shozo Iida, Kazuo Minato, Kazuhiro Sawa, Takeshi Tomita, Toru Ogawa, and Akiyoshi Ishikawa

Subjects
Nuclear and High Energy Physics, Materials science, 020209 energy, 02 engineering and technology, engineering.material, law.invention, Zirconium carbide, chemistry.chemical_compound, stomatognathic system, 0203 mechanical engineering, Coating, law, 0202 electrical engineering, electronic engineering, information engineering, Irradiation, Composite material, Burnup, Nuclear reactor, Condensed Matter Physics, 020303 mechanical engineering & transports, Nuclear Energy and Engineering, chemistry, engineering, Particle, Post Irradiation Examination, Layer (electronics), Nuclear chemistry
Abstract

The ZrC coating layer is a candidate to replace the SiC coating layer of the Triso-coated fuel particle. To compare the irradiation performance of the ZrC Triso-coated fuel particles with that of t...

Published
2000
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2. A Model to Predict the Ultimate Failure of Coated Fuel Particles During Core Heatup Events

Author

Masami Numata, Toru Ogawa, Hideshi Miyanishi, Hideo Matsushima, Hajime Sekino, Ishio Takahashi, Kousaku Fukuda, Kazuo Minato, Tadaharu Itoh, and Shigeo Kado

Subjects
chemistry.chemical_classification, Nuclear and High Energy Physics, Materials science, Mathematical model, Nuclear fuel, 020209 energy, Nuclear engineering, Radiochemistry, 02 engineering and technology, Condensed Matter Physics, 020303 mechanical engineering & transports, 0203 mechanical engineering, Nuclear Energy and Engineering, Creep, Nuclear reactor core, chemistry, 0202 electrical engineering, electronic engineering, information engineering, Ultimate failure, Compounds of carbon, Pyrolytic carbon, Graphite
Abstract

In this paper a model to predict the ultimate failure of TRISO-coated fuel particles under hypothetical core heatup events is proposed. Features of the model include the ability to treat the statistical variation of the number of coated fuel particles and to make a thermodynamic estimation of the stoichiometry of irradiated UO{sub 2} kernels and the equilibrium CO pressures. The model predictions agree well with the results of postirradiation heating tests. The thermal creep of pyrolytic carbon, however, must be taken into account to further improve the accuracy of the prediction.

Published
1991
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