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Journal Articles

Principal preferred orientation evaluation of steel materials using time-of-flight neutron diffraction

Xu, P. G.; Zhang, S.-Y.*; Harjo, S.; Vogel, S. C.*; Tomota, Yo*

Quantum Beam Science (Internet), 8(1), p.7_1 - 7_13, 2024/01

Journal Articles

Corrosion fatigue crack growth behavior of a structurally gradient steel for high-speed railway axles

Ao, N.*; Zhang, H.*; Xu, H. H.*; Wu, S. C.*; Liu, D.*; Xu, P. G.; Su, Y. H.; Kang, Q. H.*; Kang, G. Z.*

Engineering Fracture Mechanics, 281, p.109166_1 - 109166_14, 2023/03

 Times Cited Count:5 Percentile:87.64(Mechanics)

Journal Articles

Fatigue crack non-propagation behavior of a gradient steel structure from induction hardened railway axles

Zhang, H.*; Wu, S. C.*; Ao, N.*; Zhang, J. W.*; Li, H.*; Zhou, L.*; Xu, P. G.; Su, Y. H.

International Journal of Fatigue, 166, p.107296_1 - 107296_11, 2023/01

 Times Cited Count:4 Percentile:59.01(Engineering, Mechanical)

Journal Articles

Development of microstructural analysis and evaluation techniques of steel materials using RIKEN compact accelerator-driven neutron source (RANS)

Xu, P. G.; Takamura, Masato*; Iwamoto, Chihiro*; Hakoyama, Tomoyuki*; Otake, Yoshie*; Suzuki, Hiroshi

Isotope News, (774), p.7 - 10, 2021/04

no abstracts in English

Journal Articles

Effects of residual stress and plastic strain on hydrogen embrittlement of a stretch-formed TRIP-aided martensitic steel sheet

Hojo, Tomohiko*; Akiyama, Eiji*; Saito, Hiroyuki*; Shiro, Ayumi*; Yasuda, Ryo*; Shobu, Takahisa; Kinugasa, Junichiro*; Yuse, Fumio*

Corrosion Science, 177, p.108957_1 - 108957_9, 2020/12

 Times Cited Count:18 Percentile:75.61(Materials Science, Multidisciplinary)

Hydrogen assisted cracking on hemispherically-stretch-formed specimens of transformation induced plasticity-aided martensitic steel was investigated. Hydrogen charging induced cracking around the foot of the impression formed on the steel sheet, and the cracks propagated along the radial direction toward the hillside and the plains. Distributions of stress, plastic strain and volume fraction of retained austenite were analyzed employing the energy-dispersive X-ray diffraction method utilizing the synchrotron X-ray radiation at SPring-8. It was notable that the crack initiation took place in the region where the measured tensile stress was the highest. Influences of plastic strain and resulted martensitic transformation were also suggested.

Journal Articles

Application of neutron, 2; Materials evaluation using the Japan Proton Accelerator Research Complex (J-PARC)

Morooka, Satoshi

Hozengaku, 19(1), p.29 - 34, 2020/04

no abstracts in English

Journal Articles

Real time observation of martensite transformation for a 0.4C low alloyed steel by neutron diffraction

Wang, Y.*; Tomota, Yo*; Omura, Takahito*; Morooka, Satoshi; Gong, W.*; Harjo, S.

Acta Materialia, 184, p.30 - 40, 2020/02

 Times Cited Count:28 Percentile:86.1(Materials Science, Multidisciplinary)

Journal Articles

Laser cutting technology of thick steel components; Advanced technology developed at the era of decommissioning

Tamura, Koji*; Toyama, Shinichi

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 61(5), p.413 - 415, 2019/05

In decommissioning of nuclear reactors, it is necessary to disassemble the nuclear reactor structure. In addition to the conventional cutting method, the laser method has many advantages such as remote controllability and no need for replacement parts such as blades, which can be a powerful choice. Nuclear reactor structure such as a pressure vessel are made of steel materials with a thickness exceeding 100 mm, and the laser method has poor knowledge and experience in cutting such thick steel materials. Therefore, as a result of trial cutting of steel materials under various cutting conditions with the high power fiber laser which is progressively available nowadays, it has been demonstrated that laser cutting is also possible for thick plates such as those used in nuclear reactors, and cutting of thick steel plates. We also developed the cutting technology using remote control using a robot in order to apply it to the decommissioning of thick steel cutting on the spot.

Journal Articles

Study on decontamination of steel surface contaminated with uranium hexafluoride by acidic electrolytic water

Nakayama, Takuya; Nomura, Mitsuo; Mita, Yutaka; Yonekawa, Hitoshi*; Bunbai, Misako*; Yaita, Yumi*; Murata, Eiichi*; Hosaka, Katsumi*; Sugitsue, Noritake

Proceedings of 2019 International Congress on Advances in Nuclear Power Plants (ICAPP 2019) (Internet), 8 Pages, 2019/05

Clearance of contaminated metal is important for recycling and volume reduction of radioactive waste. Among applicable decontamination technologies, immersion method with ultrasonic cleaning is considered to be effective for metal materials having various shapes. in this study is to demonstrate decontamination of carbon steel contaminated by uranium hexafluoride to the target level for clearance (less than 0.04 Bq/cm$$^{2}$$), and minimize secondary waste. In this test, acidic electrolytic water, dilute hydrochloric acid, dilute sulfuric acid and ozone water with various pH and redox potential were used as decontamination solutions to be tested. We found that acidic electrolytic water is effective solution for decontamination of carbon steel contaminated by uranium hexafluoride. It could be decontaminate less than target level for clearance, and reduced secondary waste relatively.

Journal Articles

Irradiation behavior of low-copper reactor pressure vessel steels

Suzuki, Masahide; Nishiyama, Yutaka

Kinzoku, 71(8), p.42 - 45, 2001/08

no abstracts in English

Journal Articles

Development of a diagnostic technique using ultrasonic wave for evaluation of irradiation embrittlement in reactor pressure vessel materials

Ishii, Toshimitsu; Ooka, Norikazu; Niimi, Motoji; Kobayashi, Hideo*

Kinzoku, 71(8), p.20 - 24, 2001/08

no abstracts in English

JAEA Reports

Evaluation of ferromagnetic materials for induction linacs

Hashimoto, Dai; Morimoto, Iwao; Zheng, X.; Maebara, Sunao; Nakajima, Mitsuo*; Horioka, Kazuhiko*; Kono, Toshiyuki*; Shiho, Makoto

JAERI-Research 2000-018, p.66 - 0, 2000/03

JAERI-Research-2000-018.pdf:2.19MB

no abstracts in English

JAEA Reports

None

PNC TJ1211 98-005, 62 Pages, 1998/02

PNC-TJ1211-98-005.pdf:2.65MB

None

JAEA Reports

None

*; *; *; *

PNC TJ1211 98-004, 138 Pages, 1998/02

PNC-TJ1211-98-004.pdf:4.95MB

None

JAEA Reports

None

PNC TJ1150 95-007, 14 Pages, 1995/03

PNC-TJ1150-95-007.pdf:0.36MB

None

Journal Articles

Fracture toughness evaluation in the transition region of reactor pressure vessel steel

Onizawa, Kunio; Suzuki, Masahide

IWG-LMNPP-95/5 (Vol. I), 0, p.279 - 293, 1995/00

no abstracts in English

JAEA Reports

None

*

PNC TN9360 93-002, 116 Pages, 1993/11

PNC-TN9360-93-002.pdf:5.14MB

no abstracts in English

JAEA Reports

None

*

PNC TN9360 93-001, 120 Pages, 1993/06

PNC-TN9360-93-001.pdf:5.08MB

no abstracts in English

JAEA Reports

None

; Fujita, Tomoo; ; Noda, Masaru

PNC TN1410 92-055, 99 Pages, 1992/01

PNC-TN1410-92-055.pdf:3.35MB

no abstracts in English

JAEA Reports

Materials properties data sheet (No.B 01); Tensile properties data on FBR grade SUS316 (Base Metal)

; ; *; *; *; *; Yoshida, Eiichi

PNC TN9450 91-008, 38 Pages, 1991/09

PNC-TN9450-91-008.pdf:0.75MB

In order to advancement in materials strength standard on elevated temperature design guide of the FBRs and evaluation method of materials strength behavior, this report are presented about the tensile properties of FBR grade SUS316, based on the R&D results obtained through the activities of material tests. Contents of the data sheet are as follows; (1)Material : FBR grade SUS316 (Base Metal) B7 Heat 1,000mm$$times$$1,000㎜$$times$$50mm$$^{t}$$(Plate) B8 Heat 1,000㎜$$times$$1,000mm$$times$$40mm$$^{t}$$(Plate) B9 Heat 1,000mm$$times$$1,000㎜$$times$$25㎜$$^{t}$$(Plate) (2)Test temperature : RT$$sim$$750$$^{circ}$$C (3)Test method : According to JIS and FBR Metallic Materials Test Methods (4)Number of deta : 64 points

47 (Records 1-20 displayed on this page)