Application of Micromechanical Models of Ductile Fracture Initiation to Reactor Pressure Vessel Materials

Effects of Radiation on Materials: 17th International Symposium ◽

10.1520/stp16493s ◽

2009 ◽

pp. 531-531-16 ◽

Cited By ~ 1

Author(s):

R Chaouadi ◽

P De Meester ◽

E van Walle ◽

A Fabry ◽

J Van de Velde

Keyword(s):

Ductile Fracture ◽

Pressure Vessel ◽

Fracture Initiation ◽

Reactor Pressure Vessel ◽

Micromechanical Models ◽

Ductile Fracture Initiation ◽

Reactor Pressure

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Micromechanical Modeling of Ductile Fracture Initiation to Predict Fracture Toughness of Reactor Pressure Vessel Steels

Journal de Physique IV (Proceedings) ◽

10.1051/jp4:1996606 ◽

1996 ◽

Vol 06 (C6) ◽

pp. C6-53-C6-64 ◽

Cited By ~ 3

Author(s):

R. Chaouadi ◽

P. De Meester ◽

M. Scibetta

Keyword(s):

Fracture Toughness ◽

Ductile Fracture ◽

Pressure Vessel ◽

Fracture Initiation ◽

Reactor Pressure Vessel ◽

Micromechanical Modeling ◽

Pressure Vessel Steels ◽

Ductile Fracture Initiation ◽

Reactor Pressure

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Ductile fracture estimation of reactor pressure vessel under thermal shock.

TRANSACTIONS OF THE JAPAN SOCIETY OF MECHANICAL ENGINEERS Series A ◽

10.1299/kikaia.56.598 ◽

1990 ◽

Vol 56 (523) ◽

pp. 598-603

Author(s):

Jun TAKAHASHI ◽

Shinsuke SAKAI ◽

Hiroyuki OKAMURA

Keyword(s):

Ductile Fracture ◽

Thermal Shock ◽

Pressure Vessel ◽

Reactor Pressure Vessel ◽

Reactor Pressure

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Ductile Fracture Mechanisms in an A302B Modified Reactor Pressure Vessel Steel

Effects of Radiation on Materials: 17th International Symposium ◽

10.1520/stp16499s ◽

2009 ◽

pp. 637-637-23

Author(s):

LJ Cuddy ◽

MP Manahan ◽

G Brauer ◽

J Martinko

Keyword(s):

Ductile Fracture ◽

Pressure Vessel ◽

Reactor Pressure Vessel ◽

Fracture Mechanisms ◽

Pressure Vessel Steel ◽

Vessel Steel ◽

Reactor Pressure Vessel Steel ◽

Reactor Pressure

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Radiation embrittlement modelling for reactor pressure vessel steels: II. Ductile fracture toughness prediction

International Journal of Pressure Vessels and Piping ◽

10.1016/s0308-0161(99)00043-5 ◽

1999 ◽

Vol 76 (10) ◽

pp. 731-740 ◽

Cited By ~ 5

Author(s):

B.Z. Margolin ◽

V.I. Kostylev

Keyword(s):

Fracture Toughness ◽

Ductile Fracture ◽

Pressure Vessel ◽

Reactor Pressure Vessel ◽

Radiation Embrittlement ◽

Pressure Vessel Steels ◽

Ductile Fracture Toughness ◽

Reactor Pressure

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Influence of operation factors on brittle fracture initiation and critical local normal stress in SE(B) type specimens of VVER reactor pressure vessel steels

Journal of Nuclear Materials ◽

10.1016/j.jnucmat.2015.10.037 ◽

2015 ◽

Vol 467 ◽

pp. 927-936 ◽

Cited By ~ 2

Author(s):

E.A. Kuleshova ◽

A.D. Erak ◽

A.S. Kiselev ◽

S.A. Bubyakin ◽

A.P. Bandura

Keyword(s):

Brittle Fracture ◽

Normal Stress ◽

Pressure Vessel ◽

Fracture Initiation ◽

Reactor Pressure Vessel ◽

Vver Reactor ◽

Type Specimens ◽

Pressure Vessel Steels ◽

Reactor Pressure

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Effect of Neutron Irradiation on Brittle Fracture Initiation in VVER-1000 Reactor Pressure Vessel Materials

Materials Performance and Characterization ◽

10.1520/mpc20130078 ◽

2014 ◽

Vol 3 (3) ◽

pp. 20130078

Author(s):

E. A. Kuleshova ◽

M. A. Artamonov ◽

A. D. Erak

Keyword(s):

Brittle Fracture ◽

Neutron Irradiation ◽

Pressure Vessel ◽

Fracture Initiation ◽

Reactor Pressure Vessel ◽

Reactor Pressure

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The effect of residual stresses on brittle and ductile fracture initiation predicted by micromechanical models

International Journal of Fracture ◽

10.1007/bf00013236 ◽

1996 ◽

Vol 82 (4) ◽

pp. 317-333 ◽

Cited By ~ 44

Author(s):

T. L. Panontin ◽

M. R. Hill

Keyword(s):

Residual Stresses ◽

Ductile Fracture ◽

Fracture Initiation ◽

Micromechanical Models ◽

Ductile Fracture Initiation

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Influence of irradiation on the ductile fracture of a reactor pressure vessel steel

Journal of Nuclear Materials ◽

10.1016/j.jnucmat.2005.01.019 ◽

2005 ◽

Vol 341 (2-3) ◽

pp. 184-188 ◽

Cited By ~ 8

Author(s):

Petr Haušild ◽

Miloš Kytka ◽

Miroslav Karlík ◽

Pavel Pešek

Keyword(s):

Ductile Fracture ◽

Pressure Vessel ◽

Reactor Pressure Vessel ◽

Pressure Vessel Steel ◽

Vessel Steel ◽

Reactor Pressure Vessel Steel ◽

Reactor Pressure

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OS0814 Technical Review of Structural Integrity Assessment Procedure on Reactor Pressure Vessel (2) : Effects of Transient Loads on Brittle Fracture Initiation

The Proceedings of the Materials and Mechanics Conference ◽

10.1299/jsmemm.2012._os0814-1_ ◽

2012 ◽

Vol 2012 (0) ◽

pp. _OS0814-1_-_OS0814-3_

Author(s):

Kazuya OSAKABE ◽

Hiroyuki NISHIKAWA ◽

Koichi MASAKI ◽

Jinya KATSUYAMA ◽

Kunio ONIZAWA

Keyword(s):

Brittle Fracture ◽

Pressure Vessel ◽

Structural Integrity ◽

Fracture Initiation ◽

Reactor Pressure Vessel ◽

Assessment Procedure ◽

Integrity Assessment ◽

Technical Review ◽

Transient Loads ◽

Reactor Pressure

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Analyses of loads on reactor pressure vessel internals in a pressurized water reactor due to a loss-of-coolant accident considering fluid-structure interaction

Kerntechnik ◽

10.3139/124.110123 ◽

2010 ◽

Vol 75 (6) ◽

pp. 311-315

Author(s):

P. Akimov ◽

L. Obereisenbuchner

Keyword(s):

Pressure Vessel ◽

Fluid Structure Interaction ◽

Reactor Pressure Vessel ◽

Pressurized Water Reactor ◽

Pressurized Water ◽

Water Reactor ◽

Structure Interaction ◽

Loss Of Coolant Accident ◽

Loss Of Coolant ◽

Reactor Pressure

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