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Journal Articles

Plastic deformation behavior of type 316LN stainless steel in non-irradiated, thermallysensitized condition or in irradiated condition during SSRT

Miwa, Yukio; Tsukada, Takashi; Jitsukawa, Shiro

Proceedings of 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (CD-ROM), p.311 - 318, 2005/00

Plastic deformation behavior to influence the stress corrosion cracking was studied for the thermally-sensitized and the irradiated type 316LN stainless steel. SSRT was conducted at 573 K in oxygenated water (DO=10ppm) for specimens. Each of the specimens was thermally sensitized at 1033 K for 100 h or irradiated at 473 K to 1 dpa. Between these specimens, the plastic deformation behavior and the IGSCC were compared. For the irradiated specimens, plastic deformation behavior such as the work hardening capability and the maximum stress where IASCC initiated was similar to that of thermally-sensitized specimens in true stress-true strain relation. Moreover, the effect of strain rate on %IGSCC was the same each other. It was suggested from these results that for specimens irradiated around 1 dpa, the initiation mechanism of IASCC was similar to that of IGSCC for thermally-sensitized specimens.

Journal Articles

Surface decoration of stainless steel for LBE flow measurement by ultrasonic techniques

Kikuchi, Kenji; Tezuka, Masao*; Saito, Shigeru; Oigawa, Hiroyuki; Takeda, Yasushi*

Proceedings of 4th International Symposium on Ultrasonic Doppler Method for Fluid Mechanics and Fluid Engineering (ISUD-4), p.107 - 110, 2004/09

When the steel is submerged into LBE, LBE will contact with the steel except for the interface among LBE, gas and metal where the surface energy controls the shape of the free surface in LBE. It is supposed that LBE will transmit ultrasonic wave into LBE through the contacting area. However, the ultrasonic echo was too low to detect from the steel container filled with LBE. The measurement was improved by coating the interface between the steel and LBE with the SnPb solder. After an immersion test the steel surface was covered with thin LBE layer. The thickness of the layer is only 10 to 20 micron m. So it will not disturb the flow pattern where UVP is applied. Sn was not detected by X ray analyses. This is an evidence how the steel was wetted in LBE and how the ultrasonic wave transmitted though the interface of LBE and the steel.

Journal Articles

Mechanical characterization of austenitic stainless steel ion irradiated under external stress

Ioka, Ikuo; Futakawa, Masatoshi; Naito, Akira; Nanjo, Yoshiyasu*; Kiuchi, Kiyoshi; Naoe, Takashi*

Journal of Nuclear Materials, 329-333(Part2), p.1142 - 1146, 2004/08

 Times Cited Count:0 Percentile:0.01(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Corrosion-erosion test of SS316 in flowing Pb-Bi

Kikuchi, Kenji; Kurata, Yuji; Saito, Shigeru; Futakawa, Masatoshi; Sasa, Toshinobu; Oigawa, Hiroyuki; Wakai, Eiichi; Miura, Kuniaki*

Journal of Nuclear Materials, 318(1-3), p.348 - 354, 2003/05

 Times Cited Count:28 Percentile:84.98(Materials Science, Multidisciplinary)

Corrosion test of austenitic stainless tube was done under the flowing Pb-Bi condition during 3000 hrs at 450$$^{circ}$$C. Specimen is 316SS produced as a tubing form with 13.8 mm outer diameter, 2 mm thickness and 40 cm length. During the operation, maximum temperature, temperature difference and flow velocity of Pb-Bi at the specimen were kept at 450$$^{circ}$$C, 50$$^{circ}$$C, and 1m/s, respectively. After the test, specimen and components of the loop were cut and examined by optical microscope, SEM, EDX, WDX and X-ray diffraction. Pb-Bi adhered on the surface of the specimen even after Pb-Bi was drained out to the storage tank from the circulating loop. Different results from a stagnant corrosion test were that the specimen surface became rough and the corrosion rate was maximally 0.1mm/3000hrs. And mass transfer from the high temperature to the lower temperature area was observed: crystals of Fe-Cr were found on the tube surface in low-temperature part. The size of crystal was 0.1 $$sim$$ 0.2 mm. The depositing crystal was ferrite grain and the chemical composition ratio (mass%) of Fe to Cr was 9:1.

JAEA Reports

Investigation and basic evaluation for ultra-high burnup fuel cladding material

Ioka, Ikuo; Suga, Masataka*; Nagase, Fumihisa; Futakawa, Masatoshi; Kiuchi, Kiyoshi

JAERI-Tech 2001-013, 111 Pages, 2001/03

JAERI-Tech-2001-013.pdf:7.47MB

no abstracts in English

Journal Articles

Post-irradiation mechanical properties of austenitic alloys at temperatures below 703K

Jitsukawa, Shiro; Ioka, Ikuo; Hishinuma, Akimichi

Journal of Nuclear Materials, 271-272, p.167 - 172, 1999/00

 Times Cited Count:6 Percentile:45.57(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Mechanical characterization on ion irradiated thin surface layer by nanoindentation technique with inverse analysis

Ioka, Ikuo; Futakawa, Masatoshi; Wakui, Takashi*

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7) (CD-ROM), 9 Pages, 1999/00

no abstracts in English

JAEA Reports

Irradiation assisted stress corrosion cracking of austenitic stainless steels

Tsukada, Takashi

JAERI-Research 98-007, 187 Pages, 1998/03

JAERI-Research-98-007.pdf:17.46MB

no abstracts in English

Journal Articles

Development of a triple beam irradiation facility

Hamada, Shozo; Miwa, Yukio; Yamaki, Daiju; Katano, Yoshio; ; Noda, Kenji

Journal of Nuclear Materials, 258-263, p.383 - 387, 1998/00

 Times Cited Count:18 Percentile:79.15(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Effects of annealing on the tensile properties of irradiated austenitic stainless steel

Ioka, Ikuo; Naito, Akira; Shiba, Kiyoyuki; Jitsukawa, Shiro; J.P.Robertson*; Hishinuma, Akimichi

Journal of Nuclear Materials, 258-263, p.1664 - 1668, 1998/00

 Times Cited Count:2 Percentile:24.49(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Alloy development for first wall materials used in water-cooling type fusion reactors

Kiuchi, Kiyoshi; ; Hishinuma, Akimichi

Journal of Nuclear Materials, 179-181, p.477 - 480, 1991/00

 Times Cited Count:2 Percentile:31.89(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Microstructural evolution in austenitic stainless steels irradiated to 57 dpa in HFIR

Hamada, Shozo; Suzuki, Masahide; P.J.Maziasz*; Hishinuma, Akimichi

Journal of Nuclear Materials, 179-181, p.515 - 518, 1991/00

 Times Cited Count:8 Percentile:66.05(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Mechanism on low temperature sensitization of metastable austenitic stainless steels

Kiuchi, Kiyoshi; ; Kondo, Tatsuo

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku 29(2), p.177 - 188, 1988/00

no abstracts in English

JAEA Reports

Environment-Enhanced Crack Propagation of Sensitized Type 304 Austenitic Stainless Steel in Simulated BWR Environment

Nakajima, Hajime; ; Shindo, Masami; ; ; Ogawa, Yutaka; ; Kondo, Tatsuo

JAERI-M 6100, 16 Pages, 1975/04

JAERI-M-6100.pdf:1.46MB

no abstracts in English

Journal Articles

Bending Fatique Tests of Austenitic Stairless Steel at Elevated Temperatures

;

Nihon Kikai Gakkai Kanto Shibu Ibaraki Koen Rombunshu, (710-9), p.93 - 96, 1971/00

no abstracts in English

Oral presentation

Localized deformation and oxide film of neutron irradiated austenitic stainless steels

Kitsunai, Yuji*; Kasahara, Shigeki; Chimi, Yasuhiro; Nishiyama, Yutaka; Chatani, Kazuhiro*; Koshiishi, Masato*

no journal, , 

no abstracts in English

Oral presentation

Effects of DPA and helium production on radiation damage microstructures and the mechanical properties in irradiated austenitic stainless steels and ferritic steel

Wakai, Eiichi; Takaya, Shigeru; Nagae, Yuji; Suzudo, Tomoaki; Hirade, Tetsuya; Matsui, Yoshinori; Nogami, Shuhei*; Hasegawa, Akira*; Abe, Hiroaki*; Iwai, Takeo*; et al.

no journal, , 

no abstracts in English

Oral presentation

Effects of DPA and helium production on radiation damage microstructures etc. in irradiated austenitic stainless steels and ferritic steel

Wakai, Eiichi; Takaya, Shigeru; Nagae, Yuji; Hirade, Tetsuya; Matsui, Yoshinori; Nogami, Shuhei*; Hasegawa, Akira*; Aoto, Kazumi

no journal, , 

no abstracts in English

19 (Records 1-19 displayed on this page)
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