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Journal Articles

Mechanical investigation on interface failure mechanisms of dissimilar welded joints

Yamashita, Takuya; Yamashita, Hayato; Nagae, Yuji

Tetsu To Hagane, 105(1), p.96 - 104, 2019/01

 Times Cited Count:1 Percentile:9.85(Metallurgy & Metallurgical Engineering)

no abstracts in English

JAEA Reports

Long term treatment of waste TBP/n-dodecane with steam reforming system

Sone, Tomoyuki; Nakagawa, Akinori; Koyama, Hayato; Gunji, Kiyoshi; Nonaka, Kazuharu; Sasaki, Toshiki; Tashiro, Kiyoshi; Yamashita, Toshiyuki

JAEA-Technology 2009-023, 33 Pages, 2009/06

JAEA-Technology-2009-023.pdf:8.11MB

Steam reforming (SR) method consists of the gasification process in which organics are vaporized and decomposed with superheated steam and the oxidation process in which vaporized organics are decomposed by oxidizing reaction with heated air. 2,500L of waste TBP/n-dodecane contaminated with uranium was treated using the demonstration scale steam reforming system to examine the performance of the system. Results obtained in this study show that the temperature in the SR system was controlled under the self-regulation temperature, the concentration of CO and NOx in the off-gas were controlled less than 100ppm and 250ppm respectively, the distribution ratio of uranium to off-gas treatment system was under 0.12% and the gasification ratio of waste TBP was more than 99%. This long-term waste treatment test has demonstrated that the SR system can safely and effectively reduce the volume of the waste.

Oral presentation

Long-term treatment test of steam reformer for waste oraganic solvent containing uranium

Koyama, Hayato; Sone, Tomoyuki; Sasaki, Toshiki; Yamashita, Toshiyuki

no journal, , 

no abstracts in English

Oral presentation

Creep strength of modified 9Cr-1Mo steel repair welding

Yamashita, Hayato; Yamashita, Takuya; Onizawa, Takashi; Nagae, Yuji; Yamamoto, Kenji*; Shudo, Shingo*; Kawasaki, kenji*; Kubo, Koji*

no journal, , 

no abstracts in English

Oral presentation

The Material property equations for 316FR steel at extremely high temperature

Okuda, Takahiro; Yamashita, Hayato; Toyota, Kodai; Shimomura, Kenta; Onizawa, Takashi; Kato, Shoichi

no journal, , 

This study describes the setting of the material property equations of 316FR steel at an extremely high temperature which can be applied to severe accident conditions of generation IV fast reactors. 316FR steel will be applied to structural materials, e.g. reactor vessel, in the generation IV fast reactors. After the severe accident in Fukushima Daiichi Nuclear Power Plants, the evaluation of structural integrity was found to be very important severe accident condition. The development of the generation IV fast reactors requires the material properties of 316FR steel at the extremely high temperature. However, such data has not been acquired. Therefore, tensile and creep tests were carried out in the temperature range over 700$$^{circ}$$C for 316FR steel. Based on the acquired data from the tests, the equations that can evaluate the material properties of 316FR steel at the extremely high temperature were set up. They are an elasto-plastic stress-strain equation, a creep rupture equation and a creep strain equation.

Oral presentation

Development of repair welding method for advanced fast reactor candidate materials

Yamashita, Hayato

no journal, , 

no abstracts in English

Oral presentation

Interface failure assessment of dissimilar welded joints by circular notch specimen

Yamashita, Hayato; Onizawa, Takashi; Takaya, Shigeru; Enuma, Yasuhiro

no journal, , 

no abstracts in English

Oral presentation

A Proposal of a conversion method between small punch creep properties and uniaxial ones of Mod.9Cr-1Mo steel at the operating temperature of fast reactors

Yamashita, Hayato; Onizawa, Takashi; Takaya, Shigeru; Enuma, Yasuhiro; Wakai, Takashi; Kato, Shoichi; Suzuki, Akihiro*

no journal, , 

This study proposes an appropriate method to convert the load parameter in small punch creep (SPC) tests to that in uniaxial creep tests for Mod.9Cr-1Mo steel at operating temperature of future fast reactors. It is impossible to simply compare the results of SPC tests to those of uniaxial creep tests, because the load parameters in those creep tests are load and stress, respectively. Conventionally, load/stress conversion coefficient (F/$$sigma$$) has been employed to compare the results of SPC and uniaxial creep tests. Though the applicability of F/$$sigma$$ has been demonstrated in the temperature region considerably higher than 550$$^{circ}$$C that is the operating temperature of future fast reactors, the applicability has not been demonstrated at 550$$^{circ}$$C. Therefore, this paper studies an appropriate method to obtain F/$$sigma$$. F/$$sigma$$ calculated from finite element analysis (FEA) and that based on fracture ductility was too small to convert SPC results. In contrast, it was clarified that conversion was possible using F/$$sigma$$ based on Arrhenius-type equation.

Oral presentation

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