Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 23

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

Corrosion property of sheath materials using MI cables at conditions simulated severe accident

Nakano, Hiroko; Shibata, Hiroshi; Takeuchi, Tomoaki; Matsui, Yoshinori; Tsuchiya, Kunihiko

Proceedings of International Conference on Asia-Pacific Conference on Fracture and Strength 2016 (APCFS 2016) (USB Flash Drive), p.283 - 284, 2016/09

no abstracts in English

Journal Articles

Mechanical properties of weldments using irradiated stainless steel welded by the laser method for ITER blanket replacement

Yamada, Hirokazu*; Kawamura, Hiroshi; Nagao, Yoshiharu; Takada, Fumiki; Kono, Wataru*

Journal of Nuclear Materials, 355(1-3), p.119 - 123, 2006/09

 Times Cited Count:3 Percentile:25.6(Materials Science, Multidisciplinary)

In this study, the bending properties of welding joint of irradiated material and un-irradiated material (irradiated/un-irradiated joints) were investigated using SS316LN-IG, which is the candidate material for the cooling pipe of ITER. The results of this study showed that the bending position of joints using un-irradiated material was un-irradiated part and that the bending position of irradiated/irradiated joints was fusion area or HAZ (heat affected zone). Although the bending position of joints was different bor the combination pattern between irradiated and un-irradiated materials, the bending strength of joint was almost same. Additionally, it is confirmed that bending strength did not depend on the combination pattern between the irradiated and un-irradiated materials, nor on the relationship between the heat input direction and the bending load direction.

Journal Articles

The Effect of neutron irradiation on mechanical properties of YAG laser weldments using previously irradiated material

Yamada, Hirokazu*; Kawamura, Hiroshi; Tsuchiya, Kunihiko; Kalinin, G.*; Nagao, Yoshiharu; Takada, Fumiki; Nishikawa, Masahiro*

Journal of Nuclear Materials, 340(1), p.57 - 63, 2005/04

 Times Cited Count:4 Percentile:32.08(Materials Science, Multidisciplinary)

This study was performed to clear the effect of neutron re-irradiation on mechanical properties to welding material un-irradiated and irradiated stainless steel. The effect of re-irradiation to these weldaments were evaluated by tensile tests, metallographical observation and hardness test. The result of tensile tests shows that ultimate tensile strength of all joints specimen were almost similar, 0.2% yield strength and total elongation were depend on the irradiation damage and weldaments or not. Therefore, fracture mechanism was not change by re-irradiation. However, brittlement of material was depend on irradiation damage and the property of deformation was sensitive by the effect of irradiation damage or the effect of welding heat.

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:25 Percentile:84.36(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.

Journal Articles

R&D on mercury target pitting issue

Kikuchi, Kenji; Kogawa, Hiroyuki; Futakawa, Masatoshi; Ishikura, Shuichi*; Kaminaga, Masanori; Hino, Ryutaro

Journal of Nuclear Materials, 318(1-3), p.84 - 91, 2003/05

 Times Cited Count:14 Percentile:68.9(Materials Science, Multidisciplinary)

In mercury spallation target development pitting is a technical issue, which is appeared on the target vessel in conjunction with the pressure wave. Pitting is found in the off-beam line test by Split Hopkinson Pressure Bar (SHPB) test and then found in the on-beam test of mercury target at WNR of LANSCE. In SHPB tests pressure in mercury was reduced from 80, 40, 20 and 10MPa. And type 316 stainless steel was inspected before and after the impacting test at x450 magnification. Results show that over 20MPa pitting was generated. But at the lowest pressure in mercury, the number of pitting was very limited and substantial damage was small. Substantial damage by pitting is characterized by holes because mass will be removed from the wall. Depression itself may not be a substantial damage as long as it is not accompanied with holes.

Journal Articles

Corrosion-erosion of SS316 under flowing Pb-Bi

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

Nihon Kikai Gakkai 2002-Nendo Nenji Taikai Koen Rombunshu, p.273 - 274, 2002/09

Corrosion-erosion properties of type 316 austenitic stainless steel were investigated at 450oC. The study aims at developing ADS, accelerator driven system, for nuclear transmutation of long lived activated nuclei to shorter ones. After 3000 hrs flow of eutectic 45Pb-55Bi loop tubes were cut and analyzed by optical microscope, SEM, EDX, WDX and TEM. It is concluded that corrosion-erosion depth is maximally 0.1mm per 3000 hrs and Cr-Fe crystals were precipitated in the lower temperature of flowing channel. Further more inspection results of Electro Magnetic Pump, Electro Magnetic Flow meter and controlling valve were also reported. Output signal from EMF was stable after certain time duration. In this experiment oxygen content in Pb-Bi was not actively controlled but Pb-Bi was covered by 4N Argon gas.

Journal Articles

Experimental test of structural materials activation in the IFMIF neutron spectrum

Von-Moellendorff, U.*; Maekawa, Fujio; Giese, H.*; Wilson, P. P. H.*

Fusion Engineering and Design, 51-52(Part.B), p.919 - 924, 2000/11

 Times Cited Count:4 Percentile:33.53(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Validation of nuclear calculations with the FENDL/E-1.1 and JENDL fusion file based on a bulk-shielding experiment of a large type 316 stainless steel assembly

Konno, Chikara; Maekawa, Fujio; Oyama, Yukio; Ikeda, Yujiro; Wada, Masayuki*; Maekawa, Hiroshi

Fusion Technology, 34(1), p.6 - 17, 1998/08

no abstracts in English

Journal Articles

High heat flux testing of a HIP bonded first wall panel with built-in circular cooling tubes

Hatano, Toshihisa; ; ; *; *; Kitamura, Kazunori*; Kuroda, Toshimasa*; Akiba, Masato; Takatsu, Hideyuki

Fusion Engineering and Design, 39-40, p.363 - 370, 1998/00

 Times Cited Count:20 Percentile:82.55(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Summary of bulk shielding experiments for ITER at JAERI/FNS

Konno, Chikara; Maekawa, Fujio; Oyama, Yukio; Uno, Yoshitomo; Wada, Masayuki*; Maekawa, Hiroshi; Ikeda, Yujiro; Takeuchi, Hiroshi

Fusion Technology 1998, 2, p.1263 - 1266, 1998/00

no abstracts in English

Journal Articles

Validity assessment of shielding design tools for ITER through analysis of benchmark experiment on SS316/water shield conducted at FNS/JAERI

Maekawa, Fujio; Konno, Chikara; Oyama, Yukio; Ikeda, Yujiro; Wada, Masayuki*; Uno, Yoshitomo; Y.M.Verzilov*; Maekawa, Hiroshi

Fusion Technology, 30(3(PT.2B)), p.1081 - 1087, 1996/12

no abstracts in English

Journal Articles

Reweldability test of irradiated SS316 by the TIG welding method

Tsuchiya, Kunihiko; Kawamura, Hiroshi; Oyamada, Rokuro

Journal of Nuclear Materials, 233-237(PT.A), p.218 - 223, 1996/00

 Times Cited Count:9 Percentile:63.5(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Bulk shielding experiment on a large SS316/water assembly bombarded by D-T neutrons, volume II; Analysis

Maekawa, Fujio; Konno, Chikara; Wada, Masayuki*; Oyama, Yukio; Ikeda, Yujiro; Uno, Yoshitomo; Verzilov, Y.*; Maekawa, Hiroshi

JAERI-Research 95-018, 112 Pages, 1995/03

JAERI-Research-95-018.pdf:4.45MB

no abstracts in English

JAEA Reports

Bulk shielding experiment on a large SS316/water assembly bombarded by D-T neutrons, volume I; Experiment

Konno, Chikara; Maekawa, Fujio; Oyama, Yukio; Ikeda, Yujiro; Uno, Yoshitomo; Verzilov, Y.*; Wada, Masayuki*; Maekawa, Hiroshi

JAERI-Research 95-017, 71 Pages, 1995/03

JAERI-Research-95-017.pdf:3.09MB

no abstracts in English

Journal Articles

Experiment and analysis of induced radioactivity in large SS-316 stainless steel shielding material bombarded with 14MeV neutrons

Ikeda, Yujiro; Konno, Chikara; Maekawa, Fujio; Uno, Yoshitomo; Oyama, Yukio; Kosako, Kazuaki*; Maekawa, Hiroshi

Fusion Engineering and Design, 28, p.449 - 456, 1995/00

no abstracts in English

JAEA Reports

Bulk shielding experiments on large SS316 assemblies bombarded by D-T neutrons, volume II; Analysis

Maekawa, Fujio; Konno, Chikara; Kosako, Kazuaki*; Oyama, Yukio; Ikeda, Yujiro; Maekawa, Hiroshi

JAERI-Research 94-044, 143 Pages, 1994/12

JAERI-Research-94-044.pdf:5.16MB

no abstracts in English

JAEA Reports

Bulk shielding experiments on large SS316 assemblies bombarded by D-T neutrons, volume I; Experiment

Konno, Chikara; Maekawa, Fujio; Oyama, Yukio; Ikeda, Yujiro; Kosako, Kazuaki*; Maekawa, Hiroshi

JAERI-Research 94-043, 96 Pages, 1994/12

JAERI-Research-94-043.pdf:3.5MB

no abstracts in English

JAEA Reports

Pre-analyses of SS316 and SS316/Water bulk shielding experiments

Konno, Chikara; Maekawa, Fujio; *; Kosako, Kazuaki*; Ikeda, Yujiro; Oyama, Yukio; Maekawa, Hiroshi

JAERI-Tech 94-019, 43 Pages, 1994/10

JAERI-Tech-94-019.pdf:1.64MB

no abstracts in English

Journal Articles

Shielding research for next fusion devices

Maekawa, Hiroshi

Proc. of the 8th Int. Conf. on Radiation Shielding, 0, p.15 - 24, 1994/00

no abstracts in English

Journal Articles

Analysis of bulk shielding experiments on large SS316 assemblies

Maekawa, Fujio; Konno, Chikara; Kosako, Kazuaki*; Oyama, Yukio; Ikeda, Yujiro; Maekawa, Hiroshi

Fusion Technology, 21(3), p.2107 - 2111, 1992/05

no abstracts in English

23 (Records 1-20 displayed on this page)