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Journal Articles

Neutron imaging analysis of hydrogen content in pure palladium and aluminum alloys

Shimizu, Kazuyuki*; Hayashida, Hirotoshi*; Toda, Hiroyuki*; Kai, Tetsuya; Matsumoto, Yoshihiro*; Matsumoto, Yoshihisa*

Nihon Kinzoku Gakkai-Shi, 83(11), p.434 - 440, 2019/11

 Times Cited Count:1 Percentile:6.23(Metallurgy & Metallurgical Engineering)

Journal Articles

Preparation of new class composite adsorbent for enhanced palladium(II) detection and recovery

Awual, M. R.; Hasan, M. M.*; Naushad, M.*; Shiwaku, Hideaki; Yaita, Tsuyoshi

Sensors and Actuators B; Chemical, 209, p.790 - 797, 2015/03

 Times Cited Count:157 Percentile:99.25(Chemistry, Analytical)

Journal Articles

Organic-inorganic based nano-conjugate adsorbent for selective palladium(II) detection, separation and recovery

Awual, M. R.; Hasan, M. M.*; Znad, H.*

Chemical Engineering Journal, 259, p.611 - 619, 2015/01

 Times Cited Count:258 Percentile:99.34(Engineering, Environmental)

Journal Articles

Feasibility study on the blanket tritium recovery system using the palladium membrane diffuser

Kawamura, Yoshinori; Enoeda, Mikio; Yamanishi, Toshihiko; Nishi, Masataka

Fusion Engineering and Design, 81(1-7), p.809 - 814, 2006/02

 Times Cited Count:14 Percentile:68.12(Nuclear Science & Technology)

Tritium bred in the solid breeder blanket of a fusion reactor is extracted by passing of a helium sweep gas. Tritium is separated from sweep gas at the blanket tritium recovery system. Palladium membrane diffuser is one of the applicable processes for the blanket tritium recovery system. It is usually applied for hydrogen purification system such as TEP in ITER. However, it has been reported that the rate controlling step changes at lower hydrogen pressure such as the blanket sweep gas condition, and discussion about application for the blanket sweep gas condition is not enough. Recently, conceptual design of the demonstration reactor, named "DEMO2001", has been proposed from JAERI. In this report, the application of the Pd diffuser for the blanket sweep gas condition is discussed based on the condition of DEMO 2001.

Journal Articles

Study on electrolytic reduction of pertechnetate in nitric acid solution for electrolytic extraction of rare metals for future reprocessing

Asakura, Toshihide; Kim, S.-Y.; Morita, Yasuji; Ozawa, Masaki*

Journal of Nuclear and Radiochemical Sciences, 6(3), p.267 - 269, 2005/12

An electrolytic extraction (EE) method, i.e. electro-reductive deposition, of Tc from nitric acid aqueous solution was studied for future reprocessing. After 30 min of constant potential electrolysis by carbon electrode at -0.3 V vs. SSE (Standard Silver Electrode), Tc concentration in 3 M nitric acid decreased to 93 % of the initial value, which corresponds to 7 % of deposition. With co-existence of Pd, the value reached to 15 % of deposition equivalent by electrolysis at $$pm$$0.0 V vs. SSE for 60 min. An acceleration effect of Pd on Tc deposition (promoter effect) was suggested. The concentration, however, increased to the initial value after further electrolysis and competing re-dissolution of deposited Tc was also suggested. In cyclic voltammetry measurements, it was found that the deposit from Tc-Pd-Ru-Rh solution dissolved easier than that from Pd-Ru-Rh did. In electrolyzed Tc solution, an absorption peak at 482 nm was found. It can be attributed to the complex with nitrite anion, and the complex formation is proposed as one possible mechanism of Tc re-dissolution.

Journal Articles

Irradiation experiment of ZrC-coated fuel particles for high-temperature gas-cooled reactors

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

Nuclear Technology, 130(3), p.272 - 281, 2000/06

 Times Cited Count:71 Percentile:96.73(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Migration behavior of palladium in UO$$_{2}$$, III

*; Sato, Seichi*; Ohashi, Hiroshi*; Ogawa, Toru; Ito, Akinori; Fukuda, Kosaku

JAERI-M 92-118, 49 Pages, 1992/08

JAERI-M-92-118.pdf:2.54MB

no abstracts in English

JAEA Reports

Migration behavior of palladium in UO$$_{2}$$

*; Ohashi, Hiroshi*; Morozumi, Takashi *; Ogawa, Toru; Fukuda, Kosaku

JAERI-M 90-113, 46 Pages, 1990/07

JAERI-M-90-113.pdf:3.74MB

no abstracts in English

Journal Articles

Fission product palladium-silicon carbide interaction in HTGR fuel particles

Minato, Kazuo; Ogawa, Toru; Kashimura, Satoru; Fukuda, Kosaku; ; ;

Journal of Nuclear Materials, 172, p.184 - 196, 1990/00

 Times Cited Count:68 Percentile:97.81(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Assessment of fuel integrity of the High Temperature Engineering Test Reactor(HTTR) and its permissible design limit

Hayashi, Kimio; Sawa, Kazuhiro; Shiozawa, Shusaku; Fukuda, Kosaku

JAERI-M 89-162, 83 Pages, 1989/10

JAERI-M-89-162.pdf:2.53MB

no abstracts in English

Journal Articles

Development of HTGR coated particle fuels and its subjects

Nihon Genshiryoku Gakkai-Shi, 28(4), p.312 - 317, 1986/00

 Times Cited Count:0 Percentile:0.02(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Electron Probe Micro-Analysis of Irradiated Triso-Coated UO$$_{2}$$ Particles,-(II)

Minato, Kazuo; ; ; Ikawa, Katsuichi; Iwamoto, K.

JAERI-M 84-002, 56 Pages, 1984/02

JAERI-M-84-002.pdf:3.1MB

no abstracts in English

JAEA Reports

Irradiation Behaviors of Coated Fuel Particles (V) (Irradiation by JMTR 73F-13A capsule)

; ; ; Minato, Kazuo; Ikawa, Katsuichi; Iwamoto, K.;

JAERI-M 83-232, 67 Pages, 1984/01

JAERI-M-83-232.pdf:6.33MB

no abstracts in English

Journal Articles

Preliminary design of a fusion reactor fuel cleanup system by the palladium alloy membrane method

; Konishi, Satoshi; Naruse, Yuji

Nucl.Technol./Fusion, 3, p.471 - 484, 1983/00

no abstracts in English

Journal Articles

Possibility of palladium-alloy membrane pumps for thermonuclear fusion devices

Murakami, Yoshio;

Vacuum, 28(5), p.235 - 240, 1978/05

 Times Cited Count:9

no abstracts in English

24 (Records 1-20 displayed on this page)