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Journal Articles

Constraint effect on fracture behavior of underclad crack in reactor pressure vessel

Shimodaira, Masaki; Tobita, Toru; Takamizawa, Hisashi; Katsuyama, Jinya; Hanawa, Satoshi

Journal of Pressure Vessel Technology, 144(1), p.011304_1 - 011304_7, 2022/02

 Times Cited Count:0 Percentile:0(Engineering, Mechanical)

In the structural integrity assessment of a reactor pressure vessel (RPV), the fracture toughness (K$$_{Jc}$$) should be higher than the stress intensity factor at the crack tip of an under-clad crack (UCC), which is prescribed in JEAC4206-2016. However, differences in crack depth and existence of cladding between the postulated crack and fracture toughness test specimens would be affected to the plastic constraint state and K$$_{Jc}$$ evaluation. In this study, we performed fracture toughness tests and finite element analyses (FEAs) to investigate the effect of cladding on K$$_{Jc}$$ evaluation. FEA showed that the cladding decreased the plastic constraint in the UCC rather than the surface crack. Moreover, it was also found that the apparent K$$_{Jc}$$ for the UCC was higher than that for the surface crack from tests and the local approach.

JAEA Reports

Work report of International research fellow; Design review of Joyo D-type irradiation rig and Joyo irradiation techniques

Bottcher, J. T.

PNC TN9440 97-011, 215 Pages, 1997/06

PNC-TN9440-97-011.pdf:19.56MB

J.H.Bottcher started his intemational Fellow position at PNC on March 25, 1996.During his 15 months in PNC he worked in the Irradiation Section of the Experimental Reactor Division. There he worked on conceptual design reviews and related the US irradiations methodology to the members. His work extended to other Divisions at OEC and Tokai Works, mainly related to fuel development and irradiation performance. In these efforts he published two papers, wrote a desip review document, and presented six lectures on irradiated fuels and materials. In addition he participated in coordinating a new four year PNC/DOE collaborative program on irradiated steels characterization.

Journal Articles

A Method to estimate mechanical state inside fuel rod based on noise analysis

Journal of Nuclear Science and Technology, 17(11), p.811 - 821, 1980/00

 Times Cited Count:3 Percentile:41.98(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

None

Miura, Makoto; Hidaka, Yasuo; ; Omori, Takuro; Obata, Shinichi; Tanaka, Yasumasa; Shiina, Sadamu; Ogasawara, Koji

PNC TN841 79-12, 103 Pages, 1979/03

PNC-TN841-79-12.pdf:4.84MB

no abstracts in English

JAEA Reports

Preparetion of HTR Fuel Compact by Rubber Pressing

Iwamoto, K.; Tobita, Tsutomu; *; *

JAERI-M 5992, 20 Pages, 1975/02

JAERI-M-5992.pdf:0.94MB

no abstracts in English

JAEA Reports

Integrity Assessment for JPDR Pressure Vessel

; ; Ueda, Shuzo; ; ; ; ; ; ; ; et al.

JAERI 1236, 96 Pages, 1974/09

JAERI-1236.pdf:7.1MB

no abstracts in English

Oral presentation

Ion irradiation-induced microstructural changes in heat-affected zone of stainless weld overlay cladding of RPV steel

Ha, Yoosung; Takamizawa, Hisashi; Hanawa, Satoshi; Nishiyama, Yutaka; Ebisawa, Naoki*; Toyama, Takeshi*; Nagai, Yasuyoshi*

no journal, , 

Heat affected zone (HAZ) under stainless overlay cladding of RPV steel was irradiated by iron ions. To investigate the mechanism of irradiation hardening, the solute clusters distributions were confirmed by 3D-Atom Probe Tomography analysis, and the correlation between the irradiation hardening and the microstructure change in HAZ and matrix was discussed. As result of APT analysis, Cu and Si-Mn-Ni clusters were observed in irradiated area, but not in un-irradiated area. The distributions of cluster were different in coarse grain HAZ, fine grain HAZ and matrix, and the amounts of clusters in matrix were significantly lower than that in HAZ. In addition, size, chemical composition and number densities of clusters and their distributions were correlated with irradiation hardening.

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