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JAEA Reports

Compatibility of reduced activation ferritic/martensitic steel specimens with liquid Na and NaK in irradiation rig of IFMIF

Yutani, Toshiaki*; Nakamura, Hiroo; Sugimoto, Masayoshi

JAERI-Tech 2005-036, 10 Pages, 2005/06

JAERI-Tech-2005-036.pdf:2.06MB

In the high flux region of the International Fusion Materials Irradiation Facility (IFMIF), the neutron irradiation damage for iron-based alloys will exceed 20 dpa/ year. An accurate specimen temperature measurement under a large amount of nuclear heating is a key issue but the change of heat transfer of gap between irradiation specimens and specimen holder during irradiation test is inevitable, if gap is filled with an inert gas and temperature is monitored by a thermocouple buried in the specimen holder. A solution to make heat transfer predictable is to fill the gap with a liquid metal (sodium or sodium-potassium alloy). An issue of compatibility between Reduced Activation Ferritic/Martensitic steels and the liquid metalsis addressed in this paper, and some recommendations for designing irradiation rig are presented, such as a purification control before filling liquid metals, or a careful selection of material of rig to avoid carbon mass transfer.

Journal Articles

Selection of chemical forms of iodine for transmutation of $$^{129}$$I

Shirasu, Yoshiro; Minato, Kazuo

Journal of Nuclear Materials, 320(1-2), p.25 - 30, 2003/09

 Times Cited Count:3 Percentile:26.72(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Dose intercomparison studies for standardization of high-dose dosimetry in Vietnam

H.H.Mai*; N.D.Duong*; Kojima, Takuji

IAEA-TECDOC-1070, p.345 - 351, 1999/03

no abstracts in English

Journal Articles

Design and R&D activities on ceramic breeder blanket for fusion experimental reactors in JAERI

Kurasawa, Toshimasa; Takatsu, Hideyuki; Sato, Satoshi; Nakahira, Masataka; Furuya, Kazuyuki; Hashimoto, T.*; Kawamura, Hiroshi; Kuroda, Toshimasa*; Tsunematsu, Toshihide; Seki, Masahiro

Fusion Technology 1994, Vol.2, 0, p.1233 - 1236, 1995/00

no abstracts in English

JAEA Reports

A New method of extracting tritium produced in neutron-irradiated lithium-containing pellets for liquid scintillation counting

Verzilov, Y.*; Maekawa, Fujio; Oyama, Yukio; Maekawa, Hiroshi

JAERI-Research 94-042, 31 Pages, 1994/12

JAERI-Research-94-042.pdf:1.16MB

no abstracts in English

JAEA Reports

Compatibility of Heat Resistant Alloys With Boron Carbide,2

; ; ; ;

JAERI-M 82-196, 29 Pages, 1982/12

JAERI-M-82-196.pdf:2.41MB

no abstracts in English

Journal Articles

Status of liquid lithium researches on the chemistry and material compatibility

*; Katsuta, Hiroji; Furukawa, Kazuo

Nihon Kinzoku Gakkai Kaiho, 21(3), p.150 - 159, 1982/00

no abstracts in English

JAEA Reports

Compatibility of Heat Resistant Alloys with Boron Carbide

;

JAERI-M 9185, 20 Pages, 1980/11

JAERI-M-9185.pdf:3.77MB

no abstracts in English

Journal Articles

Compatibility problems in molter salts for energy storage

Furukawa, Kazuo; *

Boshoku Gijutsu, 29(4), p.185 - 195, 1980/00

no abstracts in English

Journal Articles

Air contamination effects on the compatibility of liquid lithium with molybdenum, TZM, niobium, stainless steels, nickel and hastelloy N in stainless-steel vessels at 600$$^{circ}$$C

Katsuta, Hiroji; Furukawa, Kazuo

Journal of Nuclear Materials, 71(1), p.95 - 104, 1977/01

 Times Cited Count:9

no abstracts in English

Journal Articles

Present status of future scope of fusion reactor tech; V.2 Blanket enirronments and material ampatibility

; ; ; *; ; ; Sanokawa, Konomo; ; ; ; et al.

Nihon Genshiryoku Gakkai-Shi, 15(11), p.712 - 758, 1973/11

no abstracts in English

12 (Records 1-12 displayed on this page)
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