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研究成果

学術論文

1) "Electrochemically Accelerated Stress Corrosion Cracking Test of Inconel 600 in High Temperature and High Pressure Water",

Predictive Methods for Assessing Corrosion Damage to BWR Piping and PWR Steam Generators, NACE, Library of Congress Catalog Number 81-85852, (1978), pp.370-374, Y. SAKAE, K. ONIMURA, T. YONEZAWA, T. TSURUTA.

2) "EFFECTS OF METALLURGICAL FACTORS ON CORROSION AND MASS TRANSFER OF 304 STAINLESS STEEL AND 2 1/4 Cr - 1 Mo STEEL IN SODIUM",

Proceedings of the Second International Conference on Liquid Metal Technology in Energy Production, (1979), pp.2.33-2.44,

Toshio Yonezawa, Takayuki Imazu, Tomikane Saida, Hiroshi Susukida.

3) 「304ステンレス鋼の液体ナトリウム中での腐食・質量移行に及ぼす冶金的因子の影響」

日本金属学会誌, 44-3 (1980)、pp.223-229、

米澤利夫、 今津孝幸、 斎田富兼、 薄田寛.

4) "EFFECT OF HEAT TREATMENT ON THE SUSCEPTIBILITY TO STRESS CORROSION CRACKING OF ALLOY 600",

NUCLEAR TECHNOLOGY, 55 (1981), pp.394-404,

M. KOWAKA, H. NAGANO, T. KUDO, Y. OKADA, M. YAGI, O. TAKABA,

T. YONEZAWA, K. ARIOKA.

5) "EFFECT OF HEAT TREATMENT ON STRESS CORROSION CRACKING RESISTANCE OF HIGH NICKEL ALLOYS IN HIGH TEMPERATURE WATER",  

Proceedings of the International Symposium on "Environmental Degradation of Materials in Nuclear Power Systems-water Reactors, Myrtle Beach, SC, Aug.22-25, (1983), pp.345-366,

T. Yonezawa, K. Onimura, N. Sakamoto, N. Sasaguri, H. Nakata, H. Susukida.

6) "Computer analysis of the corrosion and mass transfer of steels in sodium",

Liquid metal engineering and technology, BNES, London, 1, (1983), pp.253-257,

T. YONEZAWA, T. SAIDA, Y. WATANABE, T. KIYOKAWA, H. ATSUMO.

7) 「Alloy X-750の高温水中での応力腐食割れ抵抗に及ぼす熱処理条件の影響」

日本金属学会誌、48-3(1984)、pp.238-247、

米澤利夫、 鬼村吉郎、 坂元成夫、 笹栗信也、 中田英則、 薄田寛.

8) "EFFECT OF HEAT TREATMENT ON CORROSION RESISTANCE OF ALLOY 690",

Proceedings of the Second International Symposium on "Environmental Degradation of Materials in Nuclear Power Systems-water Reactors, Monterey, CA, Sept.9-12, (1985), pp.593-600,

T. Yonezawa, K. Onimura, N. Sasaguri, T. Kusakabe, H. Nagano, K. Yamanaka,

T. Minami, M. Inoue.

9) "EFFECT OF HEAT TREATMENT ON CORROSION RESISTANCE OF ALLOY 690",  

Proceedings of the International Symposium on Contribution of Materials Investigation to the Resolution of Problems Encountered in PWR Plants, Royal Abbey of Fontevraud, Sept.2-6, (1985), pp.289-296,

T. Yonezawa, K. Onimura, N. Sasaguri, T. Kusakabe, H. Nagano, K. Yamanaka,

T. Minami, M. Inoue.

10) 「析出硬化型 Ni 基合金の高温水中耐応力腐食割れ性に及ぼす合金元素、熱処理の影響」

   日本金属学会誌、51-4、(1987)、pp.309-318、

米澤利夫, 山口詔丈, 岡田康孝, 五十嵐正晃.

11) "Effects of Metallurgical Factors on Stress Corrosion Cracking of Ni-base Alloys in High Temperature Water",

     Proceedings of the 1988 JAIF International Conference on Water Chemistry in Nuclear Power Plants, Tokyo, Japan, April 19-22, (1988), pp.490-495,

T. Yonezawa, N. Sasaguri, K. Onimura.

12) "Effect of Chemical Compositions and Microstructure on the Stress Corrosion Cracking Resistance of Nickel Base Alloys in High Temperature Water",

Proceedings of the EVALMAT, Kobe, Japan, Nov. 20-23, 89-1(1989), pp.235-242,

T. Yonezawa, K. Onimura.

13) "Primary Water Stress Corrosion Cracking Resistance of Alloy X-750 for Guide Tube Support Pins",

Proceedings of the FONTEVRAUD II, Royal Abbey of Fontevraud, Sept. 10-14, (1990), pp.14-21,

T. YONEZAWA, K. ONIMURA, M. YONEHANA, T. FUJITANI.

14) 「アドバンスPWR蒸気発生器管用高耐食伝熱管材料の開発」、

日本金属学会会報、 29-6, (1990)、pp.487-489、

長野博夫、山中和夫、米澤利夫、日下部隆也

15) "FEASIBILITY STUDY ON NEW WEAR RESISTANT COBALT FREE ALLOY CORELOY-II" FOR NUCLEAR POWER PLANT VALVES",

Proceedings of the International Symposium on Material Chemistry in Nuclear Environment, Tsukuba, Japan, March 12-13, (1992), pp.519-524,

T. YONEZAWA, T. IWAMURA, K. NAKANISHI.

16) "ELECTRON MICRO AUTORADIOGRAPHIC OBSERVATION OF TRITIUM DISTRIBUTION ON ALLOY X750",

Proceedings of the Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, San Diego, CA, Aug. 1-5, (1993), pp.799-804,

T. Yonezawa, Y. Yamaguchi, Y. Iijima.

17) "INTERGRANULAR CRACKING IN CLADDING TUBE OF PWR RCCA RODLETS",

Proceedings of the Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, San Diego, CA, Aug. 1-5, (1993), pp.765-772,

T. Matsuoka, K. Murakami, T. Yonezawa, M. Tomimatsu, K. Morimoto, K. Goto.

18) "THERMAL TREATMENT AND PRECIPITATES MORPHOLOGY ON THE CORROSION BEHAVIOR OF PWR FUEL CLADDING TUBE MATERIALS",

Proceedings of the FONTEVRAUD III, Royal Abbey of Fontevraud, Sept. 12-16, (1994), pp.696-703,

M. Tomimatsu, K. Homma, T. Ono, T. Takahashi, Y. Shida, H. Anada, T. Yonezawa.

19) "APPLICABILITY OF COBALT FREE WEAR RESISTANT MATERIALS TO VALVES",

Proceedings of the FONTEVRAUD III, Royal Abbey of Fontevraud, Sept. 12-16, (1994), pp.116-123,

T. Yonezawa, T. Iwamura, N. Kojima, S. Suzuki.

20) "Intergranular Cracking in Cladding Tube of PWR RCCA Rodlets",

JSME International Journal Series A, 38-4, (1995), pp.515-523,

Takanori MATSUOKA, Toshio YONEZAWA, Minori TOMIMATSU, Masahiko MORI, Hisashige MYOJIN, Yoshiaki SASAKI, Masanori OOTANI, Tadahisa NAGATA.

21) "Fundamental Approach for the Developing of Cobalt-Free Wear Resistant Alloys",

Proceedings of the Seventh International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Breckenridge, CO, Aug. 7-10, (1995), pp.1247-1256,

T. Yonezawa, Y. Enomoto.

22) "THERMAL TREATMENT AND PRECIPITATES MORPHOLOGY ON THE CORROSION BEHAVIOR OF PWR FUEL CLADDING TUBE MATERIALS",

Proceedings of International Symposium on Plant Aging and Life Predictions of Corrodible Structures, Sapporo, Japan, May 15-18, (1995), pp.633-639,

T. Yonezawa, M. Tomimatsu, K. Homma, T. Ono, T. Takahashi, Y. Shida, H. Anada.

23) "ELECTRON MICRO-AUTORADIOGRAPHIC OBSERVATION OF TRITIUM DISTRIBUTION ON ALLOY X750",

  Proceedings of International Symposium on Plant Aging and Life Predictions of Corrodible Structures, Sapporo, Japan, May 15-18, (1995), pp.567-573,

T. Yonezawa, Y. Yamaguchi, Y. Iijima.

24) "SCC SUSCEPTIBILITY OF IRRADIATED AUSTENTIC STAINLESS FOR PWR",

Proceedings of Eighth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors, Amelia Island FL, Aug.10-14(1997), pp.823-830,

T. Yonezawa, K. Fujimoto, H. Kanasaki, T. Iwamura, S. Nakada, K. Ajiki, K. Sakai.

25) "Irradiation Assisted Cracking of RCCA Rodlets and Experimental Techniques for their

Improvement", Proceedings of the FONTEVRAUD IV, Royal Abbey of Fontevraud, Sept. 14-18, (1998), pp.221-235,

T. Matsuoka, Y. Yamaguchi, T. Yonezawa, K. Nakamura, R. Fukuda, S. Shiraishi.

26) "IASCC SUSCEPTIBILITY AND IT’S IMPROVEMENT OF AUSTENITIC STAINLESS STEELS FOR CORE INTERNALS OF PWR",

Proceedings of the FONTEVRAUD IV, Royal Abbey of Fontevraud, Sept. 14-18, (1998), pp.237-248,

T. Yonezawa, K. Arioka, H. Kanasaki, K. Fujimoto, E. Otsuka, S. Urata, H. Mizuta.

27) "Life Time Estimation for Cladding Tube Cracking Caused by Absorber Swelling of PWR RCCA Rodlets",

Journal of NUCLEAR SCIENCE and TECHNOLOGY, 35-8, (1998), pp.564-578, Takanori MATSUOKA, Toshio YONEZAWA, Kazuhiro NAKAMURA, Kazuo MURAKAMI, Juntarou SHIMIZU, Tadahisa NAGATA

28) "Cladding Tube Cracking Caused by Absorber Swelling for PWR RCCA Rodlets",

Journal of NUCLEAR SCIENCE and TECHNOLOGY, 36-7, (1999), pp.584-595, Takanori MATSUOKA, Youichirou YAMAGUCHI, Toshio YONEZAWA, Kazuo MURAKAMI, Shinichi SHIRAISHI, Tadahisa NAGATA.

29) "Irradiation Assisted Mechanical Cracking on Cladding Tubes of Control Rods in Nuclear Reactors",

JSME International Journal Series A, 42-3, (1999), pp.438-446,

Takanori MATSUOKA, Youichirou YAMAGUCHI, Toshio YONEZAWA, Kazuhiro NAKAMURA, Riyou FUKUDA, Shinichi SHIRAISHI.

30) "Optimized Chemical Composition and Heat Treatment Conditions of 316 CW and High-Chromium Austenitic Stainless Steels for PWR Baffle Former Bolts",

Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Newport Beach, CA, Aug. 1-5, (1999), pp.1015-1026,

T. Yonezawa, T. Iwamura, K. Fujimoto, K. Ajiki.

31) 「PWR炉内構造バッフルフォーマボルト材の粒界割れ機構に対する考察」、

日本原子力学会誌、42- 3、(2000)、pp.212-217、

米澤利夫、有岡孝司、金崎宏、藤本浩二、安食和英、松岡考典、浦田茂、

水田仁.

32) 「耐照射誘起応力腐食割れ感受性の改善を目的とした316冷間加工ステンレス鋼および高Crオーステナイト系ステンレス鋼の化学成分, 加工, 熱処理条件の最適化」、

日本金属学会誌、64-5、(2000)、pp.413-422、

米澤利夫、岩村俊彦、藤本浩二、安食和英.

33) "Simulation of Radiation Induced Segregation and PWSCC Susceptibility for Austenitic Stainless Steels",

Corrosion Engineering, 49, (2000), pp.701-720,

Koji Fujimoto, Toshio Yonezawa, Toshihiko Iwamura, Kazuhide Ajiki, Sigeru Urata.

34) "Investigation of Irradiation-Induced Intergranular Stress Corrosion Cracking Susceptibility of Austenitic Stainless Steels for PWR by Simulated Radiation-Induced Segregation Materials",

Corrosion Engineering 49, (2000), pp.655-667,

Toshio Yonezawa, Koji Fujimoto, Hiroshi Kanasaki, Toshihiko Iwamura, Shizuo Nakada, Kazuhide Ajiki, Sigeru Urata.

35) "THE EFFECT OF HYDROGEN ON INTERGRANULAR STRESS CORROSION CRACKING OF ALLOY X750 IN HIGH TEMPERATURE WATER",

Corrosion Engineering 49, (2000), pp.319-329,

T. Yonezawa, Y. Yamaguchi, Y. Iijima

36) "Improvement of IASCC Resistance for Austenitic Stainless Steels in PWR Environment",

ASTM STP 1401, (2000), pp.224-238,

Toshio Yonezawa, Koji Fujimoto, Toshihiko Iwamura, Seishi Nishida

37) 「オーステナイト系ステンレス鋼の照射誘起偏析予測とPWSCC感受性」、

材料と環境, 49-8、(2000)、pp.472-482、

藤本浩二、米澤利夫、岩村俊彦、安食和英、浦田茂.

38) 「中性子照射誘起偏析模擬材によるPWR用オーステナイト系ステンレス鋼の照射誘起粒界応力腐食割れ感受性に関する検討」、

材料と環境、49-7、(2000)、pp.437-444、    

米澤利夫、藤本浩二、金崎宏、岩村俊彦、中田志津雄、安食和英、浦田茂.

39) 「X750合金の高温水中粒界応力腐食割れに及ぼす水素の影響」、

材料と環境、49-4、 (2000)、pp.215-221、

米澤利夫、山口洋一郎、飯島嘉明.

40) "SCC Growth Rate of Nickel Based Alloy 132 Weld Metal in PWR Primary Water",

Proceedings of the Eleventh International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Stevenson, WA, Aug. 10-14, (2003), pp.1255-1265,

K.Tsutsumi, H.Kanasaki, K.Yoshimoto, Y.Nomura, S.Asada and T. Yonezawa.

41) "SCC Growth Rate of Nickel Based Alloy 132 Weld Metal in PWR Primary Water",

Proceedings of the Conference on Vessel Penetration Inspection, Crack Growth and Repair, Sept. 29 – Oct.2 (2003), CD Rom,

T. Yonezawa, K. Tsutsumi, H. Kanasaki, K. Yoshimoto, Y. Nomura, S. Asada.

42) "Effect of the Accelerate Irradiation and Hydrogen/Helium Gas on IASCC Characteristics for Highly Irradiated Austenitic Stainless Steels",

Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Salt Lake, UT, Aug. 14-18, (2005), pp.299-310,

K. Fujimoto, T. Yonezawa, E. Wachi, Y. Yamaguchi, M. Nakano, R. P. Shogan, J. P. Massoud, and T. R. Mager.

43) "Irradiation Effects in a Highly Irradiated Cold Worked Stainless Steel Removed from a Commercial PWR",

Proceedings of the Twelfth International Conference on "Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors", Salt Lake, UT, Aug. 14-18, (2005), pp.277-284,

J. Conermann, R. P. Shogan, K. Fujimoto, T. Yonezawa, Y.Yamaguchi.

44) "Effect of Temperature on the Microscopic Appearance of the Fracture Surface of Alloy 690 TT under SSRT Testing",

JSME International Journal Series A, 49-3, (2006), pp.355-362,

Y.Ito, Z.Lu, H.Miura, T.Yonezawa, T.Shoji.

45) "Metallurgical Study on IGSCC of Non-Sensitized Low-Carbon 316 Stainless Steel in BWR Environment",

Proceedings of the FONTEVRAUD VI, Royal Abbey of Fontevraud, Sept. 18-22, 1(2006), pp.19-30,

T.Yonezawa, T. Iwamura.

46) "Irradiation Assisted Stress Corrosion Cracking of Austenitic Stainless Steels in Water Reactors",

International Corrosion Engineering Conference, Soul, Korea, May 20-24, (2007),

CD-Rom,

T.Yonezawa.

47) "Mechanistic Understanding of Low Temperature Crack Propagation for Alloy 690 in Hydrogenated Water",

Proceedings of 13th International Conference on Environmental Degradation of Materials in Nuclear Systems, August 20-23, Whistler, B.C., Canada, (2007), CD-Rom,

T.Shoji, Y.Ito, Z.Lu, T.Yonezawa.

48) "Effect of Chemical Compositions and Stacking Fault Energies on IGSCC Resistance for Strain Hardened Low Carbon Austenitic Stainless Steels in High Temperature Water,"

Proceedings of 14th International Conference on Environmental Degradation of Materials in Nuclear Systems, August 23-27, Virginia Beach, VA., (2009), pp.1274- 1288, CD-Rom,

  Toshio Yonezawa, Hiroshi Kanasaki, Yasuhiro Sakaguchi, Masaki Taneike,

Suguru Ooki, Hideshi Tezuka, Kenro Takamori, Shunichi Suzuki

49) "Effect of Chemical Compositions and Heat Treatment on IGSCC Resistance for Strain Hardened Low Carbon Austenitic Stainless Steels in Oxygenated Water,"

Proceedings of the FONTEVRAUD 7, Avignon, Sept. 26-30, (2010), CD-Rom,

  Toshio Yonezawa, Hiroshi Kanasaki, Koji Fujimoto, Masaki Taneike,

Suguru Ooki, Yuichiro Sueishi, Hideshi Tezuka, Kenro Takamori, Shunichi Suzuki

50) "The effect of roll-processing orientation on stress corrosion cracking of warm-rolled 304L stainless steel in oxygenated and deoxygenated high temperature pure water",

Corrosion Science, Volume 52, Issue 8, August 2010, pp. 2547-2555

Zhanpeng Lu, Tetsuo Shoji, Tichun Dan, Yubing Qiu, Toshio Yonezawa

51) "In-situ and Ex-situ Oxide Characterization by Synchrotron X-ray (SPring-8) in Non-sensitized 316 Stainless Steel and High Temperature Water Combination",

15th International Conference on Environmental Degradation of Materials in

Nuclear Power Systems - Water Reactors-, Aug. 7-11, 2011, Colorado Springs

T.Yonezawa, M.Watanabe, T.Shobu and T.Shoji

52) "Quantitative Residual Strain Analyses on Strain Hardened Nickel Based Alloy",

15th International Conference on Environmental Degradation of Materials in

Nuclear Power Systems -Water Reactors-, Aug. 7-11, 2011, Colorado Springs

T.Yonezawa, T.Maeguchi, T.Goto, H.Juan

53) "Environmentally Assisted Crack Growth in Cold Worked Alloy 690 TT in Primary Water at Low and High Temperatures",

15th International Conference on Environmental Degradation of Materials in

Nuclear Power Systems - Water Reactors-, Aug. 7-11, 2011, Colorado Springs

Quinjia Peng, T.Shoji, J.Hou, Y.Yakeda, T.Yonezawa

54) 「BWR およびPWR 一次系模擬水質下における応力腐食割れ感受性に及ぼす冷間加工率,応力拡大係数の影響」, 

機械学会論文集A編, Vol.78, No.788(2012), pp.547-563,

矢口 誓児,米澤 利夫

55) "Measurement methods for surface oxides on SUS 316L in simulated light water reactor coolant environments using synchrotron XRD and XRF",

Journal of Nuclear Materials 434 (2013) p. 189-197

Masashi Watanabe , Toshio Yonezawa, Takahisa Shobu, Tetsuo Shoji,

国際会議発表

International Conference

1) "Effect of Heat Treatment on the Susceptibility to Stress Corrosion Cracking of Alloy600",

Proceedings of the International Conference on Materials Performance in Nuclear Steam Generators (1980),

M.Kowaka, H.Nagano, T.Kudo, Y.Okada, M.Yagi, O.Takaba, T.Yonezawa, K.Arioka.

2) "Effect of Alloying Elements and Heat Treatment on the Corrosion Resistance of Alloy 690",

EPRI Workshop on "Thermally Treated Alloy 690 Tubes for Nuclear Steam

Generators (1985),

T.Yonezawa, K.Onimura, N.Sasaguri, T.Kusakabe, H.Nagano, K.Yamanaka, T.Minami, M.Inoue.

3) "SCC Susceptibility of Irradiated Austenitic Stainless Steels for PWR",

Proceedings of the 2nd Workshop on LWR Coolant Water Radiolysis and Electrochemistry, Oct., (1999),

T.Yonezawa, K.Fujimoto, H.Kanasaki, T.Iwamura, K.Ajiki, S.Urata

4) "Effect of Chemical Compositions and Heat Treatment Conditions on the SCC Resistance of Nickel-base High Strength Alloys",

EPRI Workshop on "Advanced High Strength Materials for LWR Vessel Internal Applications (1986),

T.Yonezawa, N.Yamaguchi, Y.Okada, M.Igarashi.

5) "Effect of Chemical Compositions and Microstructure on the Stress Corrosion Cracking Resistance of Nickel Base Alloys in High Temperature Water",

EPRI Meeting on Intergranular Corrosion and Primary Water Intergranular Stress

Corrosion Cracking Mechanisms (1987),

T.Yonezawa, K.Onimura.

5) "Intergranular Cracking in Cladding Tube of PWR RCCA Rodlet",

Proceedings of the International Cooperative Research Meeting on "Environmental Assisted Cracking and Irradiation Assisted Stress Corrosion Cracking", Bristol, May, (1996),

T.Yonezawa.

6) "Stress Corrosion Cracking Susceptibility of Irradiated Austenitic Stainless Steels for PWR",

Proceedings of the International Cooperative Research Meeting on "Environmental Assisted Cracking and Irradiation Assisted Stress Corrosion      Cracking", Toronto, May, (1997),

T.Yonezawa.

7) "Round Robin Test Results 0n Alloy 600",

Proceedings of the International Cooperative Research Meeting on "Environmental Assisted Cracking and Irradiation Assisted Stress Corrosion Cracking", Hanzou, China, April, (1998),

T.Yonezawa.

8) "IASCC Susceptibility of Austenitic Stainless Steels for Core Internals of PWR",

Proceedings of the International Cooperative Research Meeting on "Environmental Assisted Cracking and Irradiation Assisted Stress Corrosion Cracking", Hanzou, China, April, (1998),

T.Yonezawa, K.Fujimoto, H.Kanasaki, E.Otsuka, H.Mizuta.

9) "Intergranular Corrosion and Intergranular Stress Corrosion Cracking of Alloy 600 in PWR Secondary Water",

Proceedings of the International Cooperative Research Meeting on "Environmental Assisted Cracking and Irradiation Assisted Stress Corrosion Cracking", Hanzou, China, April, (1998),

T.Yonezawa.

10) "Round Robin Test Results on Alloy 600",

Proceedings of the International Cooperative Research Meeting on "Environmental Assisted Cracking and Irradiation Assisted Stress Corrosion Cracking", Bristol, (1999),

T.Yonezawa.

11) "ICG-EAC Alloy 600 Round Robin Tests - Micro-structural Examination, SSRT Tests and U-bend Tests in Simulated PWR Primary Water",

Proceedings of the International Cooperative Research Meeting on "Environmental Assisted Cracking and Irradiation Assisted Stress Corrosion Cracking", April (2000),

T.Yonezawa.

12) "ICG-EAC Alloy 600 Round Robin Tests - Micro-structural Examination, SSRT Tests and U-bend Tests in Simulated PWR Primary Water",

Proceedings of the "Environmental Assisted Cracking Asia (EAC-A) Meeting", Hsinchu, Taiwan, Oct. (2000),

T.Yonezawa.

13) "The Cause of Intergranular Cracking in Baffle Former Bolts for PWR Core Internals",

Proceedings of the Asian Cooperative Group on Environmentally Assisted Cracking of Water Reactor Materials EAC-A Meeting, Hsinchu, Taiwan, Oct., (2000),

T.Yonezawa, K.Fujimoto, H.Kanasaki, T.Iwamura, K.Ajiki, S.Urata.

14) "Studies on Predominance of PWSCC for TT690",

Proceedings of the EPRI PWSCC Workshop, Feb., (2000),

K.Fujimoto, T.Yonezawa, H.Itoh, M.Mhkai, S.Urata.

15) "Round Robin Test Results on Alloy 600",

Proceedings of the "Environmental Assisted Cracking Asia (EAC-A) Meeting", Kyongju Korea, April, (2001),

T.Yonezawa.

16) "Japanese PWSCC CGR Test Data and Test Program on Alloy 600 and Weld Metals",

EPRI MRP Expert Panel CGR Review Meeting, August, (2001),

K.Tsutsumi and T.Yonezawa.

17) "Crack Growth Rate Measurement of Nickel Based Alloy Weld Metal in Simulated PWR Primary Water",

2nd EPRI MRP Expert Panel CGR Review Meeting, Oct., (2001),

K.Tsutsumi, H.Kanasaki and T.Yonezawa.

18) "The Effect of Periodic Unloading on Crack Growth Rate of Nickel Based Alloy Weld Metals in PWR Environment"

3rd EPRI MRP Expert Panel CGR Review Meeting, March, (2002),

K.Tsutsumi, H.Kanasaki and T.Yonezawa.

19) "SCC Growth Rate of Nickel Based Alloy Weld Metals in PWR Primary Water",

4th EPRI MRP Expert Panel CGR Review Meeting, April, (2002),

K.Tsutsumi, H.Kanasaki, K.Yoshimoto, Y.Nomura, S.Asada and T.Yonezawa.

19) "Proposal on SCC Test for Alloys TT690, 52, 152 under High Applied Stress in Temperature Accelerated Simulated PWR Primary Water",

5th EPRI MRP Expert Panel CGR Review Meeting, Sept., (2002),

T.Yonezawa and H.Kanasaki.

20) "SCC Growth Rate of Nickel Based Alloy Weld Metals in PWR Primary Water",

Proceedings of the "International Cooperative Group on Environmental Assisted Cracking (ICG-EAC) Meeting", Ottawa, May 11 - 16, (2003),

K.Tsutsumi, H.Kanasaki, K.Yoshimoto, Y.Nomura, S.Asada and T.Yonezawa.

21) "Tsuruga Unit-2 Pressurizer ; Leakage from the Dissimilar Weld (Alloy 600) of the Relief Nozzle",

Proceedings of the "US NRC Conference on Vessel Penetration Inspection, Cracking and Repairs", Sept. 29 – Oct.2, (2003),

T.Yonezawa.

22) "PWSCC and Hot Cracking for Weld Metals of Nickel Based Alloys",

Environmental Assisted Cracking Asia (EAC-A) Meeting, Soul, Sept., (2004), T.Yonezawa.

23) "Integrity of TT Alloy 690 Piping Material",

2005 PWSCC of Alloy 600 International Conference & Exhibit Show, Tamaya Resort, Santa Ana Pueblo, NM., March 7-10, (2005),

T.Yonezawa, K.Fujimoto, H.Kaguchi, S.Asada.

24) "Possibility of Grain Boundary Sliding or Creep as the Cause of IGSCC in High Temperature Water",

Proceedings of the "International Cooperative Group on Environmental Assisted Cracking (ICG-EAC) Meeting", Charleston, South Carolina, USA, May 14 - 19, (2006),

T.Yonezawa.

25) "Comments about the Studies on Environmental Assisted Cracking",

Environmental Assisted Cracking Asia (EAC-A) Meeting, Shanghai, Oct. 20 -21, (2006),

T.Yonezawa.

26) "TT Alloy 690 Piping Material",

EPRI MRP Expert Panel Meeting, Atlanta, VA, Oct.31-Nov.1, (2006),

T.Yonezawa.

27) "Research Trend and Future Directions for PWSCC Growth Rate Measurement",

JSPS-KOSEF Core University Program Seminar on Mechanisms of Environmentally Assisted cracking, Soul, Korea, March 14 -15, (2007),

T.Yonezawa.

28) "Comments on Cold Worked Materials for Water Reactors",

CW workshop, Mississauga, Canada, June 3-8, (2007),

T.Yonezawa.

29) "Mechanistic Understanding of Low Temperature Crack Propagation for Alloy 690 in Hydrogenated Water",

EPRI MRP Expert Panel Meeting, St. Petersburg, Fla., November 8-9, (2007), T.Shoji, T.Yonezawa, Y.Ito, Z.Lu.

30) "Mechanistic Understanding of Low Temperature Crack Propagation for Alloy 690 in Hydrogenated Water",

Environmental Assisted Cracking Asia (EAC-A) Meeting, December 18-19, (2007), Sendai, Japan,

T.Shoji, Y.Ito, Z.Lu, T.Yonezawa.

31) "Irradiation Assisted Stress Corrosion Cracking of Austenitic Stainless Steels in Water Reactors"

The 2nd Tohoku-MIT mini-workshop on Green and Clean Energy System, March 12, (2008),

T.Yonezawa.

32) "The Effect of Chemical Compositions on IGSCC Resistance for Strain Hardened Low Carbon Austenitic Stainless Steels in High Temperature Water",

Proceedings of the "International Cooperative Group on Environmental Assisted Cracking (ICG-EAC) Meeting", Baestad, Sweden, April 21-25, (2008),

T.Yonezawa, H.Kanasaki, Y.Sakaguchi, M.Taneike, S.Ooki, H.Tezuka, K,Takamori, S.Suzuki.

33) "The Possibility of Metallurgical Effects on LTCP of Alloy 690 And its Weld Metal in Hydrogenated Water",

EPRI MRP Expert Panel Alloy 690 Meeting, Los Angeles CA., November 12-14, (2008),

T.Yonezawa

34) "The Effect of Chemical Compositions and Stacking Fault Energies on IGSCC Resistance for Strain Hardened Low Carbon Austenitic Stainless Steels In High Temperature Water"

Proceedings of the "International Cooperative Group on Environmental Assisted Cracking (ICG-EAC) Meeting", Boston, MA, April 19-25, (2009),

T.Yonezawa, K.Suzuki, M.Watanabe, S.Ooki, Y.Sueishi, H.Tezuka, K.Takamori, S.Suzuki

35) "The PWSCC Resistance of TT Alloy 690 and Its Metallurgical Understanding"

EPRI MRP Expert Panel Alloy 690 Meeting, Tampa FL., December 2-4, (2009),

T.Yonezawa

36) "The Effect of Dissolved Hydrogen Content on Oxidation Behavior of Alloy 600 in Simulated PWR Primary Water",

EPRI MRP Expert Panel Alloy 690 Meeting, Tampa FL., December 2-4, (2009),

T.Yonezawa, K.Sakaguchi

37) "Coriou's crack experience in Japanese PWRs and its mitigation"

50 ans de corrosion sous contrainte des alliages de nickel au CEA-Effet Coriou

CEA Saclay, France, 26-27 Jan. 2010 

T.Yonezawa

38) "Challenging to Innovative Experiments on In-situ Oxidation Behavior of Austenitic Stainless Steel and Nickel-based Alloys in Simulated BWR and PWR Primary Water by Synchrotron X-ray",

Proceedings of the "International Cooperative Group on Environmental Assisted Cracking (ICG-EAC) Meeting", Jeju Island, South Korea, April 11-16, (2010),

T.Yonezawa, M.Watanabe, T.Shobu and T.Shoji

39) "Effect of Chemical Compositions and Heat Treatment on IGSCC Resistance for Strain Hardened Low Carbon Austenitic Stainless Steels in Oxygenated Water",

Contribution of Investigations to improve the Safety and Performance of LWRs, Avignon, France, Sept. 26-30, (2010),

T.Yonezawa, H.Kanasaki, K.Fujimoto, M.Taneikeabe, S.Ooki, Y.Sueishi, H.Tezuka, K.Takamori, S.Suzuki

40) "Metallurgical Study on PWSCC Possibility for TT Alloy 690",

EPRI MRP Expert Panel Alloy 690 Meeting, Tampa FL., Nov.30-Dec.3, (2010),

T.Yonezawa,

41) "Low Temperature Crack Propagation for Alloys 690 and 52 in Hydrogenated Water",

EPRI MRP Expert Panel Alloy 690 Meeting, Tampa FL., Nov.30-Dec.3, (2010),

T.Shoji , T.Yonezawa, Quinja Peng, Yuzuru Ito

42) "Study on Hot Cracking Characteristics of Nickel-based Alloys from the Metallurgical and Mechanical Viewpoints",

The 3rd FRRI International Workshop on Evaluation of Environmental Degradation of Materials and Proactive Aging Management, Feb., 21, (2011),

T. Yonezawa and Y. Miyahara

43) "Local Residual Stress Measurement on the Oxidized Surface of Austenitic Stainless Steel in Simulated BWR Water by Synchrotron X-ray",

Proceedings of the "International Cooperative Group on Environmental Assisted Cracking (ICG-EAC) Meeting, Dresden, Germany, May8-13, 2011

T.Yonezawa, M.Watanabe, T.Shobu and T.Shoji

44) "Metallurgical Study on PWSCC Possibility for TT Alloy 690",

Proceedings of the "International Cooperative Group on Environmental Assisted Cracking (ICG-EAC) Meeting, Dresden, Germany, May8-13, 2011

T.Yonezawa,

45) "SCC for Cold Worked Type 316 Stainless Steel in Simulated PWR Primary Water by CT Specimens",

Proceedings of the "International Cooperative Group on Environmental Assisted

Cracking (ICG-EAC) Meeting, Dresden, Germany, May8-13, 2011

Y.Miyahara, T.yonezawa

46) "Effects of Cold Working Ratio and Stress Intensity Factor on Intergranular Stress Corrosion Cracking Susceptibility of Non-sensitized Austenitic Stainless steels in Simulated BWR and PWR Primary Water",

Proceedings of the Eurocorr 2011, held at Stockholm, 4th to 8th Sept., (2011),

S.Yaguchi, T.Yonezawa

47) "Metallurgical Study on PWSCC Possibility for TT Alloy 690",

EPRI MRP Expert Panel Alloy 690 Meeting, Tampa FL., Nov.29-Dec.2, (2011),

T.Yonezawa, T. Horiuchi, N. Sato, A. Hashimoto

48) "Stress corrosion crack initiation testing of cold worked 316 stainless steel in simulated PWR primary water under the spring loaded condition",

The Minerals, Metals & Materials Society 141st TMS Annual Meeting & Exhibition,

(2012)

Y.Miyahara, T.Yonezawa

49) "Metallurgical Study on PWSCC Possibility for TT Alloy 690"

Proceedings of the "International Cooperative Group on Environmental Assisted Cracking (ICG-EAC) Meeting, Quebec City, Canada, May 13-18, (2012)

T. Yonezawa, T. Horiuchi, N. Sato, A. Hashimoto

50) "IGSCC initiation test for cold worked 316 stainless steel in simulated PWR primary water"

Proceedings of the "International Cooperative Group on Environmental Assisted Cracking (ICG-EAC) Meeting, Quebec City, Canada, May 13-18, 2012

T. Yonezawa, Y. Miyahara, A. Hashimoto

51) "Stress Corrosion Cracking Susceptibility of Strain Hardened Austenitic Stainless Steels in Simulated PWR Primary Water"

Proceedings of the "International Boiling Water Reactor and Pressurized Water Reactor Materials Reliability Conference and Exhibition National Harbor, Maryland, USA July 16- 19, 2012"

T. Yonezawa, Y. Miyahara

52) "The Effects of Metallurgical Factors on PWSCC Crack Growth Rate in Simulated PWR Primary Water for TT Alloy 690",

EPRI MRP Alloy 690/152/52 Research Collaboration Meeting, Tampa, FL, Nov. 27-29, 2012,

T. Yonezawa, Y. Miyahara, A. Hashimoto

招待講演

1) 昭和55年10月 火力発電技術協会主催「創立30周年記念火力・原子力発電大会」 にて招待講演、「FBR用304ステンレス鋼及び2・1/4Cr-1Mo鋼のNa中での腐食・質量移行」

2) 昭和63年11月 腐食・防食協会「第76回腐食防食シンポジウム」にて招待講演

「高強度Ni基合金の高温純水中の応力腐食割れ」

3) 平成2年9月 SFEN(フランス原子力学会)にて招待講演

"Primary Water Stress Corrosion Cracking Resistance of Alloy X-750 for Guide Tube Support Pins"

4) 平成4年2月 日本原子力学会主催原子力先端研究国際シンポジウムにて招待講演

"What is Expected for Material Science in Future Nuclear Energy Development?"

5) 平成6年2月 日本溶接学会主催特別研究会にて招待講演

「原子炉炉内構造部材の経年劣化について」

6) 平成8年2月 日本溶接協会主催「原子力構造機器材料・設計・施工・検査に関する講習会」にて招待講演

「軽水炉用Coフリー新耐摩耗材の開発」

7) 平成8年7月 日本学術振興会122委員会にて招待講演

「これからの原子力研究の方向」

8) 平成10年11月 日本原子力産業会議クロスオーバー研究委員会招待講演

PWR用オーステナイト系ステンレス鋼のIASCCとIACについて」

9) 平成11年7月 JRCM 環境親和性材料研究会招待講演

「PWR用材料開発の現状と今後」

10) 平成11年7月 日本学術振興会 第122委員会招待講演

「PWRにおけるIASCCの可能性と耐IASCC材料の開発」

11) 平成12年11月(財)産業創造研究所主催 原子力高度技術研究会招待講演

      「PWRにおけるNi基合金の粒界割れについて」

12) 平成13年1月(社)日本原子力学会「水化学最適化」研究専門委員会招待講演

「PWR炉内構造バッフルフォーマボルト材の粒界割れ機構に

対する考察」

  13) 平成13年5月(社)日本溶接協会主催 第28回国内シンポジウム「21世紀の材料科学と原子力を考える」招待講演 

「PWRプラントの高度化と材料科学」

14) 平成13年7月 日本原子力学会 材料部会夏季セミナー招待講演

      「PWR環境における照射誘起応力腐食割れ挙動」

  15) 平成15年6月 腐食防食協会技術賞受賞記念講演 「加圧水型原子炉用オーステナイト系ステンレス鋼の1次系水中応力腐食割れの予測と防止技術の開発」 

16) 平成16年3月 日本学術会議 消えゆく最先端技術の保全専門委員会「残すべき軽水炉材料技術」          

17) 平成17年2月 "Seminar on Materials Problems in Light Water Nuclear Reactors Status, Mitigation, Future Problems", 20-23 February, 2005 Suzhou, China  にて招待講演

"Metallurgy of high nickel alloys and welds used in LWRs"

18) 平成17年7月 日本非破壊検査協会 東北支部設立総会 特別招待講演

         「材料研究に学ぶ -トラブル対応と問題解決-」

19) 平成17年9月 第32回的場記念川渡セミナー「原子力用途から見た高合金の過去・現在・未来 」

20) 平成18年3月 日本材料学会 東北支部 特別招待講演

         「軽水炉用材料の応力腐食割れと最近の研究動向」

21) 平成18年11月 ㈱日立製作所 日立研究所 にて招待講演

         「軽水炉開発の歴史と原子力材料研究に学ぶ -トラブル対応と問題解決 - 」

22) 平成19年 5月 Asian Pacific Symposium on Corrosion in Nuclear Systems, Shanhai May, 9–10, (2007) にてKey Note Speech, 

"SCC Growth Rate Measurement Test Method for Ni-based Alloys in PWR Primary Condition",

23) 平成19年5月 KAERI 特別招待講演

         "PWSCC of Nickel Based Alloys & its Mechanism"

24) 平成19年12月 日本溶接協会主催「原子力構造機器材料・設計・施工・検査に関する講習会」にて招待講演

         「軽水炉用Ni基合金、オーステナイト系ステンレス鋼の最近の話題と研究動向」

25) 平成20年9月 住友金属㈱鋼管カンパニー特殊管事業所にて招待講演

         「TT690に関する最近の話題」

29) 平成21年4月 Korea-Japan Joint Workshop on Material Management, April 13 -14, 2009に て、招待講演 

"PWSCC Behavior and Mitigation" 

30) 平成22年1月 50 ans de corrosion sous contrainte des alliages de nickel au CEA-Effet Coriou

CEA Saclay, France, 26-27 Jan. 2010 にて招待講演

"Coriou's crack experience in Japanese PWRs and its mitigation"

31) 平成22年6月 KAERI にて招待講演

"Irradiation Assisted Stress Corrosion Cracking of Austenitic Stainless Steels in Water Reactors"

32) 平成22年6月 KAIST にて招待講演

"Most Important Stance for Basic Research"

33) 平成22年8月 フィンランドAalto大学にて招待講演

"History of Development on Hot Cracking Test Method and Still-remaining Problems in Current Hot Cracking Test Method "

34) 平成24年2月 ㈱神戸工業試験場にて招待講演 

        「材料研究・材料実験に思う」