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Journal Articles

IASCC evaluation method for irradiated core internal structures in BWR power plants

Takakura, Kenichi*; Tanaka, Shigeaki*; Nakamura, Tomomi*; Chatani, Kazuhiro*; Kaji, Yoshiyuki

Proceedings of 2010 ASME Pressure Vessels and Piping Conference (PVP 2010) (CD-ROM), 10 Pages, 2010/07

Irradiation Assisted Stress Corrosion Cracking (IASCC) is a matter of great concern as a degradation of core internal components in light water nuclear reactor. Japan Nuclear Energy Safety organization (JNES) had been conducting a project related to IASCC as a part of safety research and development study for the aging management and maintenance of the nuclear power plants. Based on the JNES project results, JNES proposed "IASCC evaluation guide for BWR core internals". The purpose of this paper is to describe the background of the guide, especially crack growth rate (CGR) tests for irradiated stainless steels.

Journal Articles

IASCC crack growth rate of neutron irradiated low carbon austenitic stainless steels in simulated BWR condition

Chatani, Kazuhiro*; Takakura, Kenichi*; Ando, Masami*; Nakata, Kiyotomo*; Tanaka, Shigeaki*; Ishiyama, Yoshihide*; Hishida, Mamoru*; Kaji, Yoshiyuki

Proceedings of 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems (CD-ROM), 9 Pages, 2007/00

Crack growth rate (CGR) tests have been conducted with neutron irradiated compact tension (CT) specimens. The CGR tests of 316L and 304L base metals irradiated from 0.516 to 1.07$$times$$10$$^{25}$$n/m$$^{2}$$ (E$$>$$1MeV), and of 316L and 308L weld metals irradiated from 0.523 to 0.541$$times$$10$$^{25}$$n/m$$^{2}$$ (E$$>$$1MeV) were performed using the reversing dc potential drop (DCPD) method under constant load at a few average stress intensity factors (K) and electrochemical corrosion potential (ECP) conditions at 288$$^{circ}$$C in water. CGRs of base metals were increased with increasing neutron fluence. Clear reductions in CGRs of base metals and weld metals were measured with decreasing ECP levels.

Oral presentation

Study for the SCC degradation incorporating dose rate effects, 1

Okita, Taira*; Koshiishi, Masato*; Hashimoto, Tsuneyuki*; Tanaka, Shigeaki*; Kodama, Mitsuhiro*; Kondo, Keietsu; Tsukada, Takashi

no journal, , 

no abstracts in English

Oral presentation

Evaluation of long-term integrity of the fuel assembly removed from the spent fuel pool, 1; Overview of Project Plan and results of FY2014

Iwanami, Masaru*; Tanaka, Shigeaki*; Ueno, Fumiyoshi

no journal, , 

no abstracts in English

Oral presentation

Evaluation of long-term integrity of the fuel assembly removed from the spent fuel pool, 1; Overview of project plan and summary of FY2015 results

Higuchi, Toru*; Ishioka, Shinichi*; Tanaka, Shigeaki*; Morishima, Yasuo*; Ueno, Fumiyoshi; Maeda, Koji

no journal, , 

no abstracts in English

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