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Journal Articles

Notch toughness evaluation of diffusion-bonded joint of alumina dispersion-strengthened copper to stainless steel

Nishi, Hiroshi

Fusion Engineering and Design, 81(1-7), p.269 - 274, 2006/02

 Times Cited Count:3 Percentile:73.3(Nuclear Science & Technology)

Tensile strength of the diffusion bonded joint was as large as that of Alumina dispersion-strengthened copper (DS Cu), however, the Charpy absorbed energy of the joint was considerably lower than that of DS Cu. Instrumented Charpy impact test and slow-bend Charpy test of diffusion bonded joints were performed to clarify the degradation of Charpy absorbed energy. Elasto-plastic analyses were also carried out in order to study the deformation behavior of the tensile and V-notched specimens for joints. As the results, the fracture behaviors of the impact and slow-bend tests were almost the same. Elasto-plastic analyses showed that the maximum strain occurred at the DS Cu apart from the interface for tensile specimen, however, the strain concentrated at the DS Cu near the interface for the notched specimen. This strain concentration arose from the mechanical heterogeneity between stainless steel and DS Cu in the bonded zone and attributed to the degradation of the absorbed energy of the joints.

Journal Articles

Neutron irradiation effect on the mechanical properties of type 316L SS welded joint

Saito, Shigeru; Fukaya, Kiyoshi*; Ishiyama, Shintaro; Amezawa, Hiroo; Yonekawa, Minoru; Takada, Fumiki; Kato, Yoshiaki; Takeda, Takashi; Takahashi, Hiroyuki*; Nakahira, Masataka

Journal of Nuclear Materials, 307-311(Part2), p.1573 - 1577, 2002/12

 Times Cited Count:1 Percentile:89.22(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Development of laser cutting/welding system for remote maintenance of ITER manifold

Yamaoka, Hiroto*; Tsuchiya, Kazuyuki*; Awano, Toshihiko*; Oka, Kiyoshi

Ishikawajima Harima Giho, 42(5), p.260 - 264, 2002/09

no abstracts in English

JAEA Reports

Deveopment of bonding techniques for cryogenic components, 1; HIP bonding tests between Ti and cryogenic stainless steels

Saito, Shigeru; Ouchi, Nobuo; Ishiyama, Shintaro; Tsuchiya, Yoshinori*; Nakajima, Hideo; Fukaya, Kiyoshi*

JAERI-Tech 2002-048, 68 Pages, 2002/05

JAERI-Tech-2002-048.pdf:7.86MB

no abstracts in English

Journal Articles

Fatigue behavior on weldment of austenitic stainless steel for ITER vacuum vessel

Nishi, Hiroshi; Eto, Motokuni; Tachibana, Katsumi; Koizumi, Koichi; Nakahira, Masataka; Takahashi, Hiroyuki*

Fusion Engineering and Design, 58-59, p.869 - 873, 2001/11

 Times Cited Count:1 Percentile:87.1(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Fatigue strength reduction factor of partial penetration weldments for ITER vacuum vessel

Nishi, Hiroshi; Eto, Motokuni; Tachibana, Katsumi; Nakahira, Masataka

Transactions of 16th International Conference on Structural Mechanics in Reactor Technology (SMiRT-16) (CD-ROM), 8 Pages, 2001/08

Fatigue test of the weldments was performed to investigate their fatigue behavior and the effect of the incomplete penetrations on the fatigue strength. Fatigue crack propagation test of their weld metals was also carried out using CT specimen. By calculating stress intensity factors of the weldments contained the incomplete penetrations and cracks using FEM analysis, the fatigue crack propagation rates of weldments were evaluated and compared those of their weld metals. Fatigue life of the weldments was evaluated based on fracture mechanics to discuss the effect of incomplete penetrations on the fatigue strength. As the results, the incomplete penetration behaved as a crack and most of total fatigue life for the weldment was crack propagation life. The crack propagation rates of weldment were in accordance with those of the weld metals. The fatigue strength of the weldment was considerably lower than that of smoothed specimen. The incomplete penetrations affected greatly the fatigue strength of the weldments even if the depth of incomplete penetrations was small.

JAEA Reports

Mechanical properties of type 316L stainless steel welded joint for vacuum vessel of ITER, 2; Neutron irradiation tests and post-irradiation experiments

Saito, Shigeru; Fukaya, Kiyoshi; Ishiyama, Shintaro; Amezawa, Hiroo; Yonekawa, Minoru; Takada, Fumiki; Kato, Yoshiaki; Takeda, Takashi; Takahashi, Hiroyuki*; Koizumi, Koichi

JAERI-Tech 2001-035, 81 Pages, 2001/06

JAERI-Tech-2001-035.pdf:18.91MB

no abstracts in English

Journal Articles

Measurement of residual stress in structural components by neutron diffraction

Hayashi, Makoto*; Okido, Shinobu*; Morii, Yukio; Minakawa, Nobuaki

Materials Science Research International, Special Technical Publication, 1, p.418 - 423, 2001/05

no abstracts in English

JAEA Reports

The 3rd technological meeting of Tokai reprocessing plant

Maki, Akira; ; Taguchi, Katsuya; ; Shimizu, Ryo; Shoji, Kenji;

JNC-TN8410 2001-012, 185 Pages, 2001/04

JNC-TN8410-2001-012.pdf:9.61MB

"The third technological meeting of Tokai Reprocessing plant (TRP)" was held in JNFL Rokkasyo site on March 14$$^{th}$$, 2001. The technical meetings have been held in the past two times. The first one was about the present status and future plan of the TRP and second one was about safety evaluation work on the TRP. At this time, the meeting focussed on the corrosion experrience, in-service inspection technology and future maintenance plan. The report contains the proceedings, transparancies and questionnaires of the meeting are contained.

Journal Articles

Low cycle fatigue strength of diffusion bonded joints of Alumina dispersion strengthened copper to stainless steel

Nishi, Hiroshi; Araki, Toshimitsu*

Journal of Nuclear Materials, 283-287(Part.2), p.1234 - 1237, 2000/12

 Times Cited Count:14 Percentile:30.74(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Analysis of weld residual stresses by FINAS (1)

*;

JNC-TN9400 2000-047, 114 Pages, 2000/03

JNC-TN9400-2000-047.pdf:8.25MB

Prediction of weld residual stresses by a general finite element code is beneficial to the improvement of the accuracy of integrity assessment and residual life assessment of FBR plants. This reports develops an evaluation method of weld residual stresses using FINAS. Firstly, we suggested a basic procedure derived from parametric analyses with a simple weld joint model. The procedure can be summarized as follows: (1)For heat conduction analysis, prepare different models corresponding to the number of layers to be modeled. Hand over the analytical results to the following model. (2)Use multi-linear stress-strain curves for modeling the stress-strain response of base metal and weld metal. Use the isotropic hardening rule. (3)When metals are melt, use a user-subroutine to keep stresses from arising. (4)Put the thermal expansion coefficient as zero when heat is being input. Then, using the above procedure and TIG welding, we predicted the weld residual stresses of plate and tube. The results agreed well with the other reports, showing the suggested procedure was reasonable.

JAEA Reports

Microstructural assessment of damaged materials in FBR assessment of creep damage in weldment

Momma, Yoshio*; *; ; ; ; Aoto, Kazumi

JNC-TN9400 2000-044, 22 Pages, 2000/03

JNC-TN9400-2000-044.pdf:1.37MB

ln the past the microstructural observation was mostly applied to understand the materials behavior qualitatively in R&D of the new materials and the life prediction for the fast breeder reactor components. However, the correlation between the changes in properties and microstrutures must be clarified to ensure the structural integrity. Particularly we are interested in the method to correlate the long-term properties and microstructural changes at high temperatures. The current research is to quantify the changes in microstructure of the weld metal for the welded structure of the reactor vessel. ln this research we have conducted creep testing of the weld metals at 823 and 873K up to 37,000h. Two types of the weld metals (16Cr-8Ni-2Mo and 18Cr-12Ni-Mo) were subjected to the creep testing. Based on the areas of the precipitates, the microstructural characterization with time and creep damage was attempted. The creep strength of the 16Cr-8Ni-2Mo weld metal is lower than that of the 18Cr-12Ni-Mo one at higher stresses, shorter times. But there is a trend toward to become similar strength with lower stresses and increasing times. The creep-rupture ductility of the 16Cr-8Ni-2Mo weld metal is superior to that of the 18Cr-12Ni-Mo one. The creep-rupture takes place at the interface of the sigma ($$sigma$$) phases precipitated in the delta ($$delta$$) ferrites at 823K lower stresses and 873K. The amount of precipitates in the 16Cr-8Ni-2Mo weld metal is smaller than that in the 18Cr-12Ni-Mo one at each temperature and stress. Also it is apparent that the amount of the precipitates is primarily responsible to the decomposition of the $$delta$$ phase, because the amount of the residual $$delta$$ ferrites measured by the Magne-Gauge reduces with times. Using the Larson-Miller parameter it was possible to correlate the amount of the precipitates linearly with the LMP values.

JAEA Reports

Fatigue crack propagation behavior at heat affected zone of zirconium weldment in boiling nitric acid solution

Motooka, Takafumi; Kiuchi, Kiyoshi

JAERI-Research 99-031, 21 Pages, 1999/04

JAERI-Research-99-031.pdf:1.89MB

no abstracts in English

JAEA Reports

None

; ; ; Yamazaki, Toshihiko; ; Kondo, Toshinari*

JNC-TN8430 99-004, 64 Pages, 1999/03

JNC-TN8430-99-004.pdf:3.92MB

None

JAEA Reports

Creep strength of Hastelloy XR welded joints

Tachibana, Katsumi; Nishi, Hiroshi; Eto, Motokuni;

JAERI-Tech 99-024, 65 Pages, 1999/03

JAERI-Tech-99-024.pdf:3.01MB

no abstracts in English

JAEA Reports

None

; ; ; Takeda, Seiichiro; *; Fujisaku, Kazuhiko*; *

PNC-TN8410 98-116, 147 Pages, 1998/08

PNC-TN8410-98-116.pdf:8.6MB

None

Journal Articles

Shape memory characteristics of neutron irradiated Ti-Ni shape memory alloy couplers

Hoshiya, Taiji; Omi, Masao; Matsui, Yoshinori; *

Journal of Nuclear Materials, 258-263(PT.B), p.2036 - 2040, 1998/00

 Times Cited Count:12 Percentile:29.05(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Investigation on the sodium leak accident of Monju; Research report on the damaged thermocouple well at the outlet of the IHX (Except the Fractured Surface)

Aoto, Kazumi; ; ; ; ; Hirakawa, Yasushi

PNC-TN9420 97-007, 786 Pages, 1997/06

PNC-TN9420-97-007.pdf:311.86MB

The results of the research on the damaged thermocouple well which caused the sodium leak accident at the outlet of the C-loop intermidiate heat exchanger (IHX) of the secondary heat transfer system of the prototype fast breeder reactor Monju are described in this report. A lot of tests, inspections, observations and measurements were carried out to confirm that the thermocouple well and its attachments to the pipe including welded part are normal by checking the possibility of weld failure or corrosion at the clearance which may cause the damage of the thermocouple well, and to get information of the dimensions relating the estimation of the leaked sodium volume and the leakage path, etc. These tests, etc., were performed for the thermocouple well except the fractured surface, the thermocouple well, the welded parts between the thermocouple well and the attachment, and between the attachment and the outlet pipe, etc., as written below. (1)Accurate measurement of the dimension. (2)Inspection to check the fixing condition between the thermocouple well and the attachment. (3)Measurement of the residual stress. (4)Non destructive testing at some points. (5)Chemical composition analysis. (6)Microscopic observation of metalogical structure at the welded part. (7)Hardness test. (8)Research on corrosion at the clearance. (9)Structure strength test of the thermocouple well. (10)Bending test of the thermocouple's sheath at high temperature.

Journal Articles

Post-irradiation weldability of type 316 stainless steel

Watanabe, Katsutoshi; Hamada, Shozo; Kodaira, Tsuneo; Hishinuma, Akimichi

ASM Conference on Welding and Joining Science and Technology, p.615 - 619, 1997/03

no abstracts in English

JAEA Reports

Evaluation on materials performance of Hastelloy alloy XR for HTTR uses, 6; Tensile and creep properties of heat exchanger tube base materials and its welded-joints

Watanabe, Katsutoshi; Shindo, Masami; Nakajima, Hajime; Koikegami, Hajime*; Higuchi, Makoto*; Nakanishi, Tsuneo*; Sahira, Kensho*; Marushichi, Koki*; Takeiri, Toshiki*; Saito, Teiichiro*; et al.

JAERI-Research 97-009, 62 Pages, 1997/02

JAERI-Research-97-009.pdf:4.82MB

no abstracts in English

47 (Records 1-20 displayed on this page)