Prediction of ductile-brittle transition for ductile crack growth in reactor pressure-vessel steels

Strength of Materials ◽

10.1007/bf02510887 ◽

1999 ◽

Vol 31 (6) ◽

pp. 525-538

Author(s):

B. Z. Margolin ◽

V. I. Kostylev

Keyword(s):

Crack Growth ◽

Pressure Vessel ◽

Reactor Pressure Vessel ◽

Ductile Crack ◽

Brittle Transition ◽

Ductile Crack Growth ◽

Pressure Vessel Steels ◽

Reactor Pressure

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Modeling for ductile-to-brittle transition under ductile crack growth for reactor pressure vessel steels

International Journal of Pressure Vessels and Piping ◽

10.1016/s0308-0161(98)00135-5 ◽

1999 ◽

Vol 76 (5) ◽

pp. 309-317 ◽

Author(s):

B.Z Margolin ◽

V.I Kostylev

Keyword(s):

Crack Growth ◽

Pressure Vessel ◽

Reactor Pressure Vessel ◽

Ductile Crack ◽

Brittle Transition ◽

Ductile Crack Growth ◽

Pressure Vessel Steels ◽

Ductile To Brittle Transition ◽

Reactor Pressure

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On the mechanisms of environment sensitive cyclic crack growth of nuclear reactor pressure vessel steels

Corrosion Science ◽

10.1016/0010-938x(83)90126-9 ◽

1983 ◽

Vol 23 (6) ◽

pp. 663-679 ◽

Author(s):

H. Hänninen ◽

K. Törrönen ◽

M. Kemppainen ◽

S. Salonen

Keyword(s):

Crack Growth ◽

Pressure Vessel ◽

Nuclear Reactor ◽

Reactor Pressure Vessel ◽

Pressure Vessel Steels ◽

Reactor Pressure

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A unified cohesive zone approach to model the ductile to brittle transition of fracture toughness in reactor pressure vessel steels

Engineering Fracture Mechanics ◽

10.1016/j.engfracmech.2014.07.029 ◽

2014 ◽

Vol 131 ◽

pp. 194-209 ◽

Author(s):

Pritam Chakraborty ◽

S. Bulent Biner

Keyword(s):

Fracture Toughness ◽

Pressure Vessel ◽

Cohesive Zone ◽

Reactor Pressure Vessel ◽

Brittle Transition ◽

Pressure Vessel Steels ◽

Ductile To Brittle Transition ◽

Reactor Pressure

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An analysis of the effects of sulphur content and potential on corrosion fatigue crack growth in reactor pressure vessel steels

Corrosion Science ◽

10.1016/0010-938x(95)00164-f ◽

1996 ◽

Vol 38 (5) ◽

pp. 755-765 ◽

Author(s):

J.D. Atkinson ◽

J. Yu ◽

Z.-Y. Chen

Keyword(s):

Fatigue Crack ◽

Fatigue Crack Growth ◽

Crack Growth ◽

Corrosion Fatigue ◽

Pressure Vessel ◽

Reactor Pressure Vessel ◽

Corrosion Fatigue Crack ◽

Pressure Vessel Steels ◽

Corrosion Fatigue Crack Growth ◽

Reactor Pressure

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Irradiation-Induced Grain-Boundary Solute Segregation and Its Effect on Ductile-to-Brittle Transition Temperature in Reactor Pressure Vessel Steels

Presented at the ASTM 24th Symposium on Effects of Radiation on Nuclear Materials and the Nuclear Fuel Cycle ◽

10.1520/stp49007s ◽

2010 ◽

pp. 153-153-11

Author(s):

Yutaka Nishiyama ◽

Masatake Yamaguchi ◽

Kunio Onizawa ◽

Akihiko Iwase ◽

Hiroshi Matsuzawa

Keyword(s):

Transition Temperature ◽

Grain Boundary ◽

Pressure Vessel ◽

Solute Segregation ◽

Reactor Pressure Vessel ◽

Brittle Transition ◽

Pressure Vessel Steels ◽

Brittle Transition Temperature ◽

Ductile To Brittle Transition ◽

Reactor Pressure

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Irradiation-Induced Grain-Boundary Solute Segregation and Its Effect on Ductile-to-Brittle Transition Temperature in Reactor Pressure Vessel Steels

Journal of ASTM International ◽

10.1520/jai101959 ◽

2009 ◽

Vol 6 (7) ◽

pp. 101959 ◽

Author(s):

Yutaka Nishiyama ◽

Masatake Yamaguchi ◽

Kunio Onizawa ◽

Akihiko Iwase ◽

Hiroshi Matsuzawa ◽

...

Keyword(s):

Transition Temperature ◽

Grain Boundary ◽

Pressure Vessel ◽

Solute Segregation ◽

Reactor Pressure Vessel ◽

Brittle Transition ◽

Pressure Vessel Steels ◽

Brittle Transition Temperature ◽

Ductile To Brittle Transition ◽

Reactor Pressure

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Errata: “Corrosion Fatique Crack Growth in Reactor Pressure Vessel Steels in PWR Primary Water” (Journal of Pressure Vessel Technology, 1983, 105, pp. 245–254) and “Development of Engineering Codes of Practice for Corrosion Fatigue” (Journal of Pressure Vessel Technology, 1983, 105, pp. 255–262)

Journal of Pressure Vessel Technology ◽

10.1115/1.3264285 ◽

1983 ◽

Vol 105 (4) ◽

pp. 308-308

Author(s):

P. M. Scott ◽

A. E. Truswell ◽

B. Tomkins ◽

A. J. E. Foreman

Keyword(s):

Crack Growth ◽

Corrosion Fatigue ◽

Pressure Vessel ◽

Reactor Pressure Vessel ◽

Codes Of Practice ◽

Pressure Vessel Steels ◽

Primary Water ◽

Reactor Pressure

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Acoustic emission and ductile crack growth in pressure-vessel steels

Metal Science ◽

10.1179/030634577790432802 ◽

1977 ◽

Vol 11 (11) ◽

pp. 531-536 ◽

Author(s):

G. Clark ◽

J. F. Knott

Keyword(s):

Acoustic Emission ◽

Crack Growth ◽

Pressure Vessel ◽

Ductile Crack ◽

Ductile Crack Growth ◽

Pressure Vessel Steels

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Grain Boundary Phosphorous Segregation and Its Influence on the Ductile Brittle Transition Temperature in Reactor Pressure Vessel Steels

Effects of Radiation on Materials: 21st International Symposium ◽

10.1520/stp11257s ◽

2008 ◽

pp. 565-565-14 ◽

Author(s):

A Kimura ◽

M Shibata ◽

R Kasada ◽

H Nakata ◽

K Fujii ◽

...

Keyword(s):

Transition Temperature ◽

Grain Boundary ◽

Pressure Vessel ◽

Reactor Pressure Vessel ◽

Brittle Transition ◽

Ductile Brittle Transition Temperature ◽

Pressure Vessel Steels ◽

Brittle Transition Temperature ◽

Reactor Pressure

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Grain Boundary Phosphorous Segregation and Its Influence on the Ductile Brittle Transition Temperature in Reactor Pressure Vessel Steels

Journal of ASTM International ◽

10.1520/jai11369 ◽

2004 ◽

Vol 1 (9) ◽

pp. 11369 ◽

Author(s):

A Kimura ◽

M Shibata ◽

R Kasada ◽

H Nakata ◽

K Fujii ◽

...

Keyword(s):

Transition Temperature ◽

Grain Boundary ◽

Pressure Vessel ◽

Reactor Pressure Vessel ◽

Brittle Transition ◽

Ductile Brittle Transition Temperature ◽

Pressure Vessel Steels ◽

Brittle Transition Temperature ◽

Reactor Pressure

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