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JAEA Reports

Seismic evaluation of the CRDM and the CRDM guide tube for JRR-3

Kikuchi, Masanobu; Kawamura, Sho; Hosoya, Toshiaki

JAEA-Technology 2021-040, 86 Pages, 2023/02

JAEA-Technology-2021-040.pdf:3.26MB

In JRR-3, in response to new regulatory standard for research and test reactor which is enforced December 2013, we established new design basis ground motion for confirming new regulatory standard and carried out seismic evaluations of the appointments, instruments and structures which are installed in JRR-3 by using that earthquake motion. This report shows that the result of evaluations by fatigue strength evaluation, which is more detailed evaluation approach, about Control Rod Drive Mechanism (CRDM) and the CRDM Guide Tube that have gotten the serious result of seismic safety margin by using time history response analysis method. As a result, it was confirmed that CRDM and the CRDM Guide Tube have sufficient seismic safety margin.

Journal Articles

Tensile and fatigue strength of free-standing CVD diamond

Davies, A. R.*; Field, J. E.*; Takahashi, Koji; Hada, Kazuhiko

Diamond and Related Materials, 14(1), p.6 - 10, 2005/01

 Times Cited Count:20 Percentile:60.46(Materials Science, Multidisciplinary)

A CVD diamond is finding increased application and it is important to study its fatigue properties. The present paper describes research on a batch of di-electric grade CVD material. It was obtained that tensile strength at the nucleation side and the growth were side 690$$pm$$90MPa and 280$$pm$$30MPa, respectively. Some samples survived at least 95% of their critical fracture stress for 10$$^{7}$$ cycles without fatiguing.

Journal Articles

Elastic-plastic FEM analysis on low cycle fatigue behavior for alumina dispersion-strengthened copper/stainless steel joint

Nishi, Hiroshi

Journal of Nuclear Materials, 329-333(Part2), p.1567 - 1570, 2004/08

 Times Cited Count:9 Percentile:52.68(Materials Science, Multidisciplinary)

Elastic-plastic finite element analysis was performed for low cycle fatigue behavior of stainless steel/alumina-dispersion-strengthened copper (DS Cu) joint in order to investigate the fatigue life and the fracture behavior of the joint. As the results, a strain concentration was occurred near the interface of DS Cu for small strain range, however, in the DS Cu for large strain range. The fatigue life and fracture point were evaluated taking account for the strain concentration. The fatigue life and fracture point were consistent with those of the low cycle fatigue test.

JAEA Reports

Structural integrity of heavy liquid-metal target installed in spallation neutron facility, 4; Consideration by fracture mechanics of target container window

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

JAERI-Tech 2003-093, 55 Pages, 2004/01

JAERI-Tech-2003-093.pdf:5.41MB

To estimate the structural integrity of the heavy liquid-metal (Hg) target used in a MW-class neutron scattering facility, static and dynamic stress behaviors due to the incident of a 1MW-pulsed proton beam were analyzed. In the analyses, two-type target containers with semi-cylindrical type and flat type window were used as analytical models of the structural analysis codes LS-DYNA. As a result, it is confirmed that the stress generated by dynamic thermal shock becomes the largest at the center of window, and the flat type window is more advantageous from the structural viewpoint than the semi-cylindrical type window. It was confirmed to erosion damage the target container by mercury's becoming negative pressure in the window and generating the cavitation by the experiment. Therefore, it has been understood that the point top of the window was in the compression stress field by the steady state thermal stress because of the evaluation from destroying the dynamic viewpoint for the crack in the generated pit and the pit point, and the crack did not progress.

Journal Articles

Tensile and fatigue strength of a through-wall-electron-beam-welded joint for the vacuum vessel of a fusion reactor

Suzuki, Takayuki*; Usami, Saburo*; Kimura, Takae*; Koizumi, Koichi; Nakahira, Masataka; Takahashi, Hiroyuki*

Proceedings of 55th Annual Assembly of International Institute of Welding (IIW2002), 16 Pages, 2002/06

A new type of welded joint for the outer wall and rib of a double-walled vacuum vessel of a fusion reactor has been developed. The joint is manufactured by through-wall electron-beam welding (TW-EBW), in which the beam is injected from the outside of the outer wall. Static and fatigue tests are carried out on one-bead-specimens under an axial load and two-bead-specimens under a bending load. The experimental results are analytically investigated by FEM. Although this joint is partially penetrated, the net yield strength of the bead is increased by the plastic constraint due to triaxial tensile stress in the weldment. This phenomenon reduces the mean equivalent stress on the bead cross section, and the gross strength of the joint is close to that of a full thickness welded joint. The fatigue-strength reduction factor for low-cycle fatigue life is a little larger than four. The calculated fatigue-crack growth rate in the joint is conservatively calculated by using the maximum stress intensity factor of the crack and the fatigue-crack growth rate given in ASME Code Section XI.

Journal Articles

Change in electrical resistivity of nuclear graphite and carbon materials during low cycle fatigue

Eto, Motokuni; Konishi, Takashi*

Tanso, (186), p.30 - 35, 1999/00

no abstracts in English

Journal Articles

Biaxial fatigue strength of a fine-grained isotropic graphite for HTTR

Eto, Motokuni; Ishiyama, Shintaro

Journal of Nuclear Science and Technology, 35(11), p.808 - 815, 1998/11

no abstracts in English

Journal Articles

Biaxial fatigue strength of a fine-grained isotropic graphite for HTTR

Eto, Motokuni; Ishiyama, Shintaro

Journal of Nuclear Science and Technology, 35(11), p.808 - 815, 1998/11

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

The Fatigue strength of graphite and carbon materials for HTTR core components

Eto, Motokuni; Arai, Taketoshi; Konishi, Takashi*

JAERI-Research 98-024, 58 Pages, 1998/03

JAERI-Research-98-024.pdf:2.03MB

no abstracts in English

Journal Articles

Biaxial fatigue strength of a fine-grained isotropic graphite for HTGR

Eto, Motokuni; Ishiyama, Shintaro

23nd Biennial Conference on Carbon (CARBON '97) Extended Abstracts and Program, Vol,2, p.276 - 277, 1997/00

no abstracts in English

Journal Articles

Effect of oxidation in air on the fatigue strength of fine-grained isotropic graphite for HTGR

; ;

Nihon Genshiryoku Gakkai-Shi, 29(7), p.651 - 655, 1987/07

 Times Cited Count:7 Percentile:60.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

The crack initiation and growth behavior for high temperature creep-fatigue interaction in notched specimen of Ni-based alloy

; *; ;

Nihon Kikai Gakkai Rombunshu, A, 52(477), p.1228 - 1231, 1986/00

no abstracts in English

Journal Articles

Experimental evaluation of torsional fatigne strength of welded bellows and application to design of fusion device

; Yamamoto, Masahiro; ; *; *; *; *

Journal of Nuclear Science and Technology, 21(5), p.341 - 355, 1984/00

 Times Cited Count:4 Percentile:45.52(Nuclear Science & Technology)

no abstracts in English

Oral presentation

Improvement of fatigue strength and biocompatibility of Ti-6Al-4V for dental implant by low energy laser peening

Iino, Yuki*; Akita, Koichi*; Sano, Yuji*; Mizuta, Yoshio*; Tamaki, Satoshi*; Shobu, Takahisa

no journal, , 

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