Institution
Japan Nuclear Cycle Development Institute
About: Japan Nuclear Cycle Development Institute is a based out in . It is known for research contribution in the topics: MOX fuel & Neutron. The organization has 816 authors who have published 792 publications receiving 12649 citations.
Topics: MOX fuel, Neutron, Uranium, Creep, Fission products
Papers published on a yearly basis
Papers
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TL;DR: In this article, the authors reviewed the JNC activities on ODS steel development as "nano-composite materials" and concluded that the ODS-technology development achieved in the field of fast reactors should be effectively spun off to the fusion reactor first wall and blanket structural materials to allow for safe and economical reactor design.
673 citations
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TL;DR: In this paper, the general governing equations for coupled thermohydromechanical (THM) processes in saturated and unsaturated geologic formations are presented and four finite element codes for modeling of such system are reviewed.
246 citations
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TL;DR: In this article, the possible extent of reaction between bentonite and cement pore fluids was simulated using the reaction-transport model, PRECIP, and the results showed complex fronts of mineral dissolution and growth driven by the relative rates of these processes for different minerals.
186 citations
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TL;DR: In this article, Fe-0.12C-9Cr-2W ODS martensitic steel claddings were developed by cold-rolling under the softened ferrite phase induced by slow cooling from austenite phase to break up substantially elongated grains produced by cold rolling at the final heat treatment.
Abstract: For use as fuel cladding of liquid metal fast reactors, Fe-0.12C-9Cr-2W ODS martensitic steel claddings were developed by cold-rolling under the softened ferrite phase induced by slow cooling from austenite phase, subsequently by ferrite to austenite phase transformation to break up substantially elongated grains produced by cold-rolling at the final heat-treatment. The produced claddings showed noticeable improvement in tensile and creep rupture strength that are considerably superior to PNC-FMS and even austenitic PNC316 at higher temperature and extended time to rupture. The strength improvement is mainly attributed to titanium addition in ODS martensitic steels through its reduction of Y2O3 particle size and shortening inter-particles spacing. The behavior of oxide particle size reduction is associated with stoichiometry between Y2O3 and TiO2.
184 citations
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TL;DR: In this article, the high temperature strengthening mechanism of previously manufactured 12Cr-ODS ferritic steel claddings was clarified, and the grain boundary sliding associated with grain morphology was considered to be controlled by the near Σ11, Σ and Σ19 coincidence boundaries with a (110) common axis.
Abstract: The high temperature strengthening mechanism of previously manufactured 12Cr-ODS ferritic steel claddings was clarified. In the recrystallized 12Cr-2W-0.3Ti-0.24Y2O3-ODS ferritic steel cladding, αY2TiO5 type complex oxide formation was responsible for the drastic reduction of oxide particle size and the resulting shortened distance between particles, which led to superior internal creep rupture strength at 973 K because of the high resistance to gliding dislocation. Internal creep deformation was considered to be controlled by the grain boundary sliding associated with grain morphology: the near Σ11, Σ and Σ19 coincidence boundaries with a (110) common axis.
168 citations
Authors
Showing all 816 results
Name | H-index | Papers | Citations |
---|---|---|---|
Akihiko Kimura | 44 | 345 | 7890 |
Shigeharu Ukai | 41 | 282 | 6867 |
Toshinori Sato | 36 | 325 | 5111 |
Sheng Xu | 35 | 128 | 3453 |
Takeshi Naganuma | 33 | 161 | 3633 |
Mineo Kumazawa | 33 | 95 | 4223 |
Mikio Kumagai | 30 | 104 | 2179 |
Hideo Harada | 27 | 332 | 2962 |
Satoshi Ohtsuka | 26 | 99 | 1958 |
Anyun Zhang | 25 | 77 | 1453 |
Hideo Sakasegawa | 22 | 67 | 1234 |
Takeji Kaito | 21 | 83 | 1500 |
Shinji Takeuchi | 21 | 60 | 2318 |
Kazunori Yamamoto | 21 | 53 | 2133 |
Masayuki Fujiwara | 20 | 35 | 2428 |