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Journal Articles

Removal and recovery of uranium from solid wastes by supercritical carbon dioxide fluid leaching method

Meguro, Yoshihiro; Tomioka, Osamu; Imai, Tomoki*; Fujimoto, Shigeyuki*; Nakashima, Mikio; Yoshida, Zenko; Honda, Tadashi*; Koya, Fumio*; Kitamura, Nobu*; Wada, Ryutaro*; et al.

Proceedings of International Waste Management Symposium 2004 (WM '04) (CD-ROM), 8 Pages, 2004/03

Supercritical CO$$_{2}$$ fluid leaching (SFL) method using supercritical CO$$_{2}$$ fluid containing a complex of HNO$$_{3}$$ - tri-n-butyl phosphate (TBP) was applied to removal of uranium from radioactive solid wastes. Sea sands, incineration ashes and porous alumina bricks were employed as matrixes of simulated solid wastes. Real radioactive incineration ash wastes and firebrick wastes were also subjected to the SFL treatment. It was found that uranium could be efficiently removed from both of the simulated wastes and real wastes by the SFL method. The removal efficiency of uranium from the real waste was lower than that from the corresponding artificial waste. About 1 g and 35 mg of uranium were recovered from 10 g of the real ash waste and 37 g of the real firebrick waste, respectively.

Journal Articles

ITER engineering design

Shimomura, Yasuo; Tsunematsu, Toshihide; Yamamoto, Shin; Maruyama, So; Mizoguchi, Tadanori*; Takahashi, Yoshikazu; Yoshida, Kiyoshi; Kitamura, Kazunori*; Ioki, Kimihiro*; Inoue, Takashi; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 78(Suppl.), 224 Pages, 2002/01

no abstracts in English

Journal Articles

Determination of $$gamma$$-ray efficiency curves for volume samples by the combination of Monte Carlo simulations and point source calibration

Saegusa, Jun; Oishi, Tetsuya; Kawasaki, Katsuya; Yoshizawa, Michio; Yoshida, Makoto; Sawahata, Tadahiro*; Honda, Tetsutaro*

Journal of Nuclear Science and Technology, 37(12), p.1075 - 1081, 2000/12

no abstracts in English

JAEA Reports

Safety analysis and evaluation of the next fusion devices

*; *; *; Kawai, Masayoshi*; *; Yamaoka, Mitsuaki*; *; Seki, Yasushi

JAERI-M 88-251, 303 Pages, 1988/12

JAERI-M-88-251.pdf:6.12MB

no abstracts in English

JAEA Reports

A Conceptual design of a negative-ion-grounded advanced tokamak reactor; NAVIGATOR(FER)

Yamamoto, Shin; Ohara, Yoshihiro; Tani, Keiji; Nishio, Satoshi; Okumura, Yoshikazu; Araki, Masanori; Azumi, Masafumi; R.S.Devoto*; Fujisawa, Noboru; Hitoki, Shigehisa*; et al.

JAERI-M 88-086, 183 Pages, 1988/05

JAERI-M-88-086.pdf:4.57MB

no abstracts in English

JAEA Reports

Japanese contributions to IAEA INTOR Workshop,Phase two A,Part 3; Chapter XI; System analysis of INTOR-like designs

Mizoguchi, Tadanori*; Iida, Hiromasa; Sugihara, Masayoshi; Fujisawa, Noboru; *; *; *; Nakajima, Kunihiko*; Nishio, Satoshi; *; et al.

JAERI-M 88-062, 77 Pages, 1988/03

JAERI-M-88-062.pdf:1.46MB

no abstracts in English

JAEA Reports

Japanese contributions to IAEA INTOR Workshop,Phase two A,Part 3; Chapter I; Introduction,Chapter II; Summary

; Tomabechi, Ken*; Fujisawa, Noboru; Iida, Hiromasa; Tsunematsu, Toshihide; *; Mizoguchi, Tadanori*; *; *; Sugihara, Masayoshi; et al.

JAERI-M 88-014, 146 Pages, 1988/02

JAERI-M-88-014.pdf:3.46MB

no abstracts in English

JAEA Reports

Japanese contributions to IAEA INTOR Workshop, Phase two A,Part 3; Chapter VII; Configuration and maintenance

Iida, Hiromasa; *; *; Adachi, Junichi*; *; *; Hamajima, Takataro*; Hatayama, Akiyoshi*; *; *; et al.

JAERI-M 88-011, 261 Pages, 1988/02

JAERI-M-88-011.pdf:6.44MB

no abstracts in English

JAEA Reports

Main engineering features driving design concept and engineering design constraints; Conceptual design study of FY86 FER

*; *; *; *; Nakajima, Kunihiko*; Sugihara, Masayoshi; Yamamoto, Shin; Iida, Hiromasa; Fujisawa, Noboru; Mizoguchi, Tadanori*; et al.

JAERI-M 87-137, 72 Pages, 1987/09

JAERI-M-87-137.pdf:1.32MB

no abstracts in English

JAEA Reports

Japanese Contributions to IAEA INTOR Workshop,Phase Two A,Part 2 Chapter VI:Maintainability

; *; ; ; *; *; *; *; *; *; et al.

JAERI-M 85-078, 207 Pages, 1985/07

JAERI-M-85-078.pdf:5.28MB

no abstracts in English

JAEA Reports

Release of Metal Fission Products from Coated Particle Fuel (Sweep-Gas Capsules 74F9J,75F4A,and 75F5A)

; ; ; Tobita, Tsutomu; ; ; ; ; ; Iwamoto, K.; et al.

JAERI-M 85-041, 48 Pages, 1985/03

JAERI-M-85-041.pdf:1.33MB

no abstracts in English

Journal Articles

Radiation Damage Studies of Graphite in Japan

; ;

Peaceful Uses of Atomic Energy, 10, p.367 - 382, 1972/00

no abstracts in English

12 (Records 1-12 displayed on this page)
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