Refine your search:     
Report No.
 - 
Search Results: Records 1-13 displayed on this page of 13
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Intelligible seminar on fusion reactors, 8; Fuel cycling system for tritium recovery

Fukada, Satoshi*; Hayashi, Takumi

Nihon Genshiryoku Gakkai-Shi, 47(9), p.623 - 629, 2005/09

no abstracts in English

Journal Articles

Operation results and technologies on the safety systems of the Tritium Process Laboratory at the Japan Atomic Energy Research Institute

Yamanishi, Toshihiko

Purazuma, Kaku Yugo Gakkai-Shi, 78(12), p.1295 - 1300, 2002/12

no abstracts in English

JAEA Reports

None

JNC TN1400 2000-001, 371 Pages, 2000/01

JNC-TN1400-2000-001.pdf:12.26MB

no abstracts in English

JAEA Reports

Journal Articles

Overview of tritium safety technology at the tritium process laboratory of JAERI

Hayashi, Takumi; Okuno, Kenji

Journal of Fusion Energy, 12(1-2), p.21 - 25, 1993/00

 Times Cited Count:3 Percentile:38.1(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Tritium production and safe handling

Hoshasen, 12(3), p.77 - 85, 1986/00

no abstracts in English

JAEA Reports

In-Pile Experiment for Tritium Release from Li$$_{2}$$O under High Neutron Fluence --- Detritiation and Tritium Monitoring ---

; ; Kurasawa, T.; ; ; ; ; ; Naruse, Yuji;

JAERI-M 83-204, 29 Pages, 1983/11

JAERI-M-83-204.pdf:1.0MB

no abstracts in English

Journal Articles

JAEA Reports

None

JAERI 6017, 47 Pages, 1966/08

JAERI-6017.pdf:2.56MB

no abstracts in English

JAEA Reports

None

JAERI 6008, 25 Pages, 1961/08

JAERI-6008.pdf:1.83MB

no abstracts in English

JAEA Reports

None

JAERI 6007, 52 Pages, 1961/03

JAERI-6007.pdf:2.66MB

no abstracts in English

Oral presentation

Activities summary on lithium target system and test facilities in IFMIF/EVEDA Project, 4; Technology development for lithium safety handling

Hirakawa, Yasushi; Furukawa, Tomohiro; Iijima, Minoru; Kondo, Hiroo; Kanemura, Takuji; Wakai, Eiichi

no journal, , 

Lithium, which is used as the neutron source of the International Fusion Materials Irradiation Facility (IFMIF), reacts easily with nitrogen, oxygen and humidity in atmosphere. In this study, the R&D results on the lithium safety handling are presented in this study. The contents are (a) lithium fire extinguishing, (b) chemical reaction of lithium at elevated temperature, (c) lithium cleaning for the components and (d) impurity analysis of lithium.

Oral presentation

Dissolution of lithium compounds in ethanol

Hirakawa, Yasushi; Furukawa, Tomohiro

no journal, , 

At the replacement of the components such as the target assembly of the International Fusion Irradiation Facility (IFMIF), cleaning of the adhered lithium on the inner surface of the components is required for the long term storage. In this study, we performed the dissolution experiment of lithium compounds in ethanol, and the dependency on temperature and time were clarified.

13 (Records 1-13 displayed on this page)
  • 1