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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:2 Percentile:17.03(Materials Science, Multidisciplinary)

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:2 Percentile:19.66(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

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

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

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

JAEA Reports

High-temperature strength test of the liner material (II); High-temperature tensile and creep property of SM400B welded joint material

; Aoto, Kazumi;

PNC TN9450 97-012, 75 Pages, 1996/11

PNC-TN9450-97-012.pdf:25.58MB

This report described the results of tensile and creep tests under a high temperature with the welded joints of liner plate (SM400B) used in SHTS cells of leaked sodium storage system of "NONJU plant". Results obtained are summarized as follows. (1)Foundmental high temperature strength characteristics data of the welded Joints were acquired. (2)There is no effect of heat treatment and cut-out direction on tensile strength and rupture elongation of liner plate. (3)The rupture ductility (rupture elongation and reduction of area) is lower than one of the base metal. Especially, rapidly droped in the temperature over 800 $$^{circ}$$C. (4)The creep strength of welded joint is almost same as one of the based metal. It will be estimated the effect of change of the micro-structure on the ductility. (5)Generally speaking, two phases of $$alpha$$ phase and $$gamma$$ phase intermingled exist under about 800$$^{circ}$$C, and $$alpha$$ phases transform to the $$gamma$$ phase under about 900$$^{circ}$$C over Ac3 transformation point. Then the grain boundary in HAZ, begin to grow, and the intergranular failure appears in over 900$$^{circ}$$C. The results will be applied to evaluate the stractural integrity of SHTS cells of leaked sodium storage system of "MONJU plant". (SHTS ; Secondary Heat Transfer System)

Journal Articles

Residual stress distribution in corbon steel pipe welded joints measured by neutron diffraction

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

Zairyo, 45(7), p.772 - 778, 1996/07

no abstracts in English

JAEA Reports

Development of creep-fatigue evaluation method for welde structures considering metallurgical and geometrical discontinuities; Application of elastic follow-up model to welded joints

kasahara, Naoto

PNC TN9410 95-213, 38 Pages, 1995/08

PNC-TN9410-95-213.pdf:1.72MB

In order to evaluate thermal transient strength of welded components in nuclear plants, conventional structural design codes provide conservative strength reduction factors, which are desired to be rationalized. Author extended the generalized clastic follow-up model to evaluate main causes of strength reduction of welded joints. As main causes of strength reduction of welded joints subjected to cyclic thermal transients, attention was given to (1)Metallurgical discontinuity in which the different deformation response between base metal and weld metal can result in nonuniform stresses and strain across the weldment, (2)Structural discontinuity at penetration beads of welded joints, and (3)Degradation of Weld Metal. In order to evaluate (1) and (2) of above factors, an elastic follow-up model was successfully applied. Thermal transient strength test results provide further substantiation of the validity of the elastic follow-up model for ensuring adequate life in elevated temperature component weldments. Author applied the creep-fatigue life prediction methods based on the elastic follow-up model to evaluate test results of a welded vessel model. Proposed method was proved to be adequate through comparison of predicted damagc with observed cracks data.

Journal Articles

Journal Articles

Studies on the porosity in welding joints, 3rd report; Results of experimental welding

; ; Ando, Yoshio*

Yosetsu Gakkai-Shi, 31(12), p.980 - 985, 1962/00

no abstracts in English

Oral presentation

Factor analysis of interface failure mechanism for dissimilar weld joints

Yamashita, Takuya; Takaya, Shigeru; Nagae, Yuji; Date, Shingo*; Tomobe, Masato*

no journal, , 

no abstracts in English

Oral presentation

Corrosion behavior of weld joint of carbon steel overpack under geological environment, 2; Corrosion behavior of engineering scale testing

Yamazaki, Kazutoshi*; Takao, Hajime*; Kikuchi, Takahiro*; Kuriki, Yoshiro*; Kobayashi, Masato*; Kawakubo, Masahiro*; Shirase, Mitsuyasu*; Iwata, Yumiko*; Tochigi, Yoshikatsu*; Nakayama, Gen*; et al.

no journal, , 

Among factors affecting the corrosion behavior of carbon steel overpack, in order to consider materials (size) and realistic environmental factors which are difficult to reproduce in the laboratory scale test, engineering scale tests in the underground environment were carried out. A mock-up test of the same scale was also carried out on the ground with the aim of controlling and evaluating factors that govern the corrosion phenomenon. As a result of the test for about 3 years, there was no big difference between the average corrosion amount and the maximum corrosion amount of the simulated overpack base metal and the welded part. On the other hand, unlike the laboratory scale test, localization of corrosion due to the adhesion between the buffer material and the simulated overpack was also confirmed during the initial transient period.

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