Advanced material tokamak experiment (AMTEX) program with ferritic steel for JFT-2M

Sato, Masayasu; Miura, Yukitoshi; Kimura, Haruyuki; Kawashima, Hisato; Sengoku, Seio; Yamamoto, Masahiro; ; Shibata, Takatoshi; Akiyama, Takashi*; Abe, Mitsushi*; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 75(6), p.741 - 749, 1999/06

http://ci.nii.ac.jp/naid/110003826520

no abstracts in English

ATR Demonstration reactor integrity verification test for the pressur tube rolled joint portion (Fiscal 1988)

; ; ; ;

PNC TN9410 94-052, 251 Pages, 1994/01

PNC-TN9410-94-052.pdf:9.33MB

The structure of the pressure tube rolled joint portion for the ATR Demonstration Reactor is somewhat changed from that for Fugen, in order reduce the residual stress around the portion. Therefore, Constant Temperature Endurance Test and Thermal Cycle Endurance Test have been conducted under the reactor operating conditions except irradiation to examine the rolled joint integrity. (1)Constant Temperature Endurance Test. In fiscal 1988, Constant Temperature Endurance Test have been performed in the Component Test Loop for 2,033 hours under the reactor operating conditions (pressure 75kg/cm, temperature 280C) for the JP-3 specimen (total testing period 4,033 hours) and the JP-4, JP-5 specimens (total testing period 9,533 hours). After the endurance test it was found by the helium leak test that the rolled joint tightness was maintained enough. Therefore, it was confirmed that the reduction of the residual atress at the rolled joint portion which occurred at the initial stage of the operation did not affect the rolled joint tightness. (2)Thermal Cycle Endurance Test. The helium leak test and the ultrasonic flaw detection test were performed before and after Thermal Cycle Endurance Test (the unmber of thermal cycle increaced from 60 times to 140 times in fisical 1988), of which results showed the integrity of the rolled joint tightness and no crack propagation near the rolled joint portion. Therefore, it was confirmed that 140 times thermal cycle which was the design value for the reactor life of 30 years did not affect the rolled joint tightness and the initiation and propagation of a crack even for the specimen with 200 ppm hydrogen.

Gamma-radiolysis of water and some aqueous solutions under N gas bubbling

; Tachikawa, Enzo; ;

Journal of Nuclear Science and Technology, 10(4), p.234 - 241, 1973/04

https://doi.org/10.3327/jnst.10.234

no abstracts in English

On the Mechanism of H-Atom Formation by Reaction of Electrons in Frozen Acidic Solutions at 77°K

Sasaki, Teikichi; ; *

Bull.Chem.Soc.Jap., 45(8), p.2383 - 2385, 1972/00

https://doi.org/10.1246/bcsj.45.2383

no abstracts in English

Gamma-Radiolysis of Aqueous Bolic Acid Solution

; ; *

Journal of Nuclear Science and Technology, 6(4), p.163 - 169, 1969/04

https://doi.org/10.3327/jnst.6.163

no abstracts in English

Radiation effects in dimethyl-diphenyl siloxane copolymer, 2; Effect of temperature of crosslinking during irradiation

Journal of the Physical Society of Japan, 18(39), p.387 - 396, 1963/00

https://doi.org/10.1143/JPSJ.18.387

no abstracts in English

Radiation effects on polyethelene at a high dose of -ray irradiation

; ; Masao Inoue*

Reports on Progress in Polymer Physics in Japan, 5, P. 267, 1962/00

no abstracts in English

Temperature effect on the crosslinking in irradiated siloxane polymers

;

Reports on Progress in Polymer Physics in Japan, 5, P. 273, 1962/00

no abstracts in English

Effect of gamma radiations on silicone rubber

;

Oyo Butsuri, 30(2), p.97 - 104, 1961/00

http://joi.jlc.jst.go.jp/JST.Journalarchive/oubutsu1932/11.97

no abstracts in English

Radiation Stability of the Radiation Shielding Windows Glasses

; *;

JAERI 1010, 10 Pages, 1960/07

JAERI-1010.pdf:0.56MB

no abstracts in English