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Journal Articles

Recontamination prevention technologies to prevent radioactive cesium from its runoff from not decontaminated forests to living areas

Nagasu, Ryosuke*; Tanabe, Daijiro*; Yokotsuka, Satoshi*; Kumazawa, Noriyuki*; Ajiki, Takaya*; Aizawa, Yusuke*; Naganawa, Hirochika; Nagano, Tetsushi; Yanase, Nobuyuki*; Mitamura, Hisayoshi*; et al.

Kankyo Joka Gijutsu, 17(2), p.58 - 61, 2018/03

A new technology to suppress cesium migration from forests has been developed collaboratively by Ibaraki University, Kumagai-gumi Co., Ltd. and its group company, Technos, and JAEA. The new technology utilizes polyelectrolytes (polymers with electric charges) and clay minerals to control Cs migration with the aid of natural forces such as rainfall and rainwater runoff. In Imitate-mura, Fukushima, verification tests of the new technology have been performed and its effect on controlling Cs migration from forests to grass farm adjoining the forests has been proven.

Journal Articles

Evaluation of mechanical properties and nano-meso structures of 9-11%Cr ODS steels

Tanno, Takashi; Otsuka, Satoshi; Yano, Yasuhide; Kaito, Takeji; Oba, Yojiro*; Onuma, Masato*; Koyama, Shinichi; Tanaka, Kenya

Journal of Nuclear Materials, 440(1-3), p.568 - 574, 2013/09

 Times Cited Count:12 Percentile:73.42(Materials Science, Multidisciplinary)

This study carried out mechanical tests and microstructure characterizations of several 9Cr and 11Cr-ODS tempered martensitic steels, and discussed the appropriate chemical composition range of 11Cr-ODS tempered martensitic steel from the viewpoint of high-temperature strength improvement. It was shown that the residual $$alpha$$-ferrite fraction in 11Cr-ODS steel was successfully controlled to the same level as the 9Cr-ODS steel by selecting the matrix chemical compositions on the basis of the multi-component phase diagram. The tensile strength decreased with decreasing W content from 2.0 to 1.4 wt%. On the other hand, creep strength at 973 K did not degrade by the decreasing W content. Both tensile strength and creep strength increased with increasing population of the nano-sized oxide particles. Small angle X-ray scattering analysis revealed that titanium and excess oxygen contents were key parameters in order to improve the dispersion condition of nano-sized oxide particles.

JAEA Reports

None

Otsuka, Jiro; Sawada; Sasaki; Maeda*; Uesugi*

JNC TN4520 2005-001, 85 Pages, 2005/09

JNC-TN4520-2005-001.pdf:18.04MB

JAEA Reports

Training report of the FBR cycle training facility in 2004FY

Watanabe, Tomoo; Ozawa, Kazumasa; Otsuka, Jiro; Sasaki, Kazuichi; Sawada, Makoto

JNC TN4440 2005-001, 40 Pages, 2005/07

JNC-TN4440-2005-001.pdf:1.85MB

no abstracts in English

JAEA Reports

None

Otsuka, Jiro; Kawanishi, Tomotake*; Koyagishi, Naoki; Sasaki, Kazuichi; Sawada, Makoto

JNC TN4410 2004-010, 12 Pages, 2005/03

JNC-TN4410-2004-010.pdf:2.34MB

None

JAEA Reports

Training report of the FBR cycle training facility in 2004FY

Watanabe, Tomoo; Ozawa, Kazumasa; Otsuka, Jiro; SASAKI, Kazuhito; Sawada, Makoto

JNC TN4410 2004-003, 20 Pages, 2004/07

JNC-TN4410-2004-003.pdf:0.66MB

The FBR cycle training facility consists of sodium handling training facility and maintenance training facility, and is being contributed to train for the operators and maintenance workers of the prototype fast breeder reactor "Monju". So far, some training courses have been added to the both training courses of sodium handling technologies maintenance technologies in every year in order to carry out be significant training for preparation of Monju restarting. As encouragement of the sodium handling technology training in 2003FY, the sodium heat transfer basic course was equipped as the 9th sodium handling training course with the aims of learning basic principal technology regarding sodium heat transfer. While, for the maintenance training course, a named "Monju Systems Learning Training Course", which aims to learn necessary knowledge as the engineers related Monju development, was provided newly in this year as an improvement concerned the maintenance course. In 2003FY, nine sodium handling technology training courses were carried out total 33 times and 235 trainees took part in those training courses. Also, nine training courses concerning the maintenance technology held 15 times and total 113 trainees participated. On the other hand, the 4th special lecture related sodium technology by France sodium school instructor was held on Mar. 15-17 and 34 trainees participated. Consequently, a cumulative trainees since October in 2000 opened the FBR cycle training facility reached to 1,236 so for.

JAEA Reports

None

Otsuka, Jiro; Yasui, Hisatoshi*; Yoshida, Kazuo*; *; Koyagishi, Naoki; SASAKI, Kazuhito; Sawada, Makoto

JNC TN4410 2004-001, 31 Pages, 2004/06

JNC-TN4410-2004-001.pdf:4.19MB

None

JAEA Reports

None

Otsuka, Jiro; Kawanishi, Tomotake*; Koyagishi, Naoki; Sasaki, Kazuichi; Sawada, Makoto

JNC TN4410 2003-009, 31 Pages, 2003/12

JNC-TN4410-2003-009.pdf:0.75MB

None

Journal Articles

Development of a man/machine interface system for the JT-60 upgrade

Yonekawa, Izuru; Shimono, Mitsugu; Totsuka, Toshiyuki; Yamagishi, Kojiro

Proc. of the 14th Symp. on Fusion Engineering,Vol. 2, p.798 - 801, 1992/00

no abstracts in English

Oral presentation

Creep strength and nano-macro structure of high-Cr martensitic steel

Tanno, Takashi; Otsuka, Satoshi; Kaito, Takeji; Yano, Yasuhide; Koyama, Shinichi; Tanaka, Kenya; Oba, Yojiro*; Onuma, Masato*

no journal, , 

The 9Cr-ODS martensitic steel is under development as first candidate material for fast reactor long life fuel cladding. It should have high temperature strength, irradiation resistance and productibility. The 11Cr-ODS steels with additional corrosion resistance by Cr enrichment are also under development. And the evaluation of their applicability for cladding material is in progress. Trial manufacture, creep test and nano/macro structure evaluation of several ODS steels were carried out to modify the chemical composition and manufacturing process of the 11Cr-ODS steel. Uni-axial creep strength of manufactured 11Cr-ODS steels were equal to or higher than that of 9Cr-ODS steel. The strength of 11Cr-ODS steels with 0.3wt% Ti was slightly higher than that with 0.2wt% Ti. The size and number density of dispersed-oxide depended on the amount of added Ti and extra-oxygen.

Oral presentation

High temperature strength and nano/meso structure evaluation of High Cr-ODS steels

Tanno, Takashi; Otsuka, Satoshi; Yano, Yasuhide; Tanaka, Kenya; Oba, Yojiro*; Onuma, Masato*

no journal, , 

The 9Cr-ODS martensitic steel is under development as first candidate material for fast reactor long life fuel cladding, because of its superior high temperature strength, irradiation resistance and productivility. The 11Cr-ODS steels with additional corrosion resistance by Cr enrichment are also under development, and the evaluation of their applicability for cladding material is in progress. Trial manufacturing, high temperature tensile test, creep test and nano/meso structure evaluation of several ODS steels were carried out to modify the chemical composition and manufacturing process of the 11Cr-ODS steel. Uni-axial creep strength of manufactured 11Cr-ODS steels were equal to or higher than that of 9Cr-ODS steel. The residual $$alpha$$-ferrite fraction in 11Cr-ODS steels was also controlled at the same level as that of the 9Cr-ODS steel. The creep strength had a linear correlation with the dispersion condition, which is defined by the size and number density of dispersed-oxide.

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