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2013
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Journal of Nuclear Materials, 2010
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Deterministic assessment of reactor pressure vessel integrity under pressurised thermal shock
v venkat
International Journal of Pressure Vessels and Piping, 1998
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Multicriteria Analytical Model for Mechanical Integrity Prognostics of Reactor Pressure Vessels Manufactured from Forged and Rolled Steels
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Mathematics, 2022
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Assessment of brittle strength of nuclear reactor pressure vessel steel upon warm prestressing
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Strength of Materials, 2010
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The effect of radiation-induced structural changes under accelerated irradiation on the behavior of water-cooled reactor pressure vessel steels
K. Prikhodko
2014
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Critical fracture stress and fracture strain models for the prediction of lower and upper shelf toughness in nuclear pressure vessel steels
Robert Ritchie
Metallurgical Transactions A, 1980
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Lifetime analysis of wwer reactor pressure vessel internals concerning material degradation
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Strength of Materials, 2010
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Small specimen predictions of fracture toughness for nuclear pressure vessel steels
Dick Wullaert
Nuclear Engineering and Design, 1980
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Structural integrity assessment of reactor pressure vessels during pressurized thermal shock
Young Hyun Choi
Journal of Mechanical Science and Technology, 2008
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Probabilistic Fracture Mechanics Analysis of the Beltline of A PWR Nuclear Power Plant Pressure Vessel
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2021 International Conference on Automation, Control and Mechatronics for Industry 4.0 (ACMI), 2021
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Master curve techniques to evaluate an irradiation embrittlement of nuclear reactor pressure vessels for a long-term operation
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International Journal of Pressure Vessels and Piping, 2008
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Linear elastic vs elastic-plastic fracture mechanics methods in nuclear vessel integrity assessments
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International Journal of Pressure Vessels and Piping, 1997
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Probabilistic assessment of reactor pressure vessel integrity under pressurised thermal shock
venkat raj
International Journal of Pressure Vessels and Piping, 1999
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Crack initiation and arrest in a pressurized thermal shock test for a model pressure vessel made of VVER-440 reactor pressure vessel steel
Pekka Nurkkala
Nuclear Engineering and Design, 1995
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An Evaluation of Through-Thickness Changes in Primary Damage Production in Commercial Reactor Pressure Vessels
Roger Stoller
Effects of Radiation on Materials: 20th International Symposium, 2000
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Demonstration of Structural Integrity of Boiling Water Reactor Pressure Vessels Under Ultimate Response Guideline Operation
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Nuclear Technology, 2020
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Interim results of the reactor pressure vessel materials evaluation within the framework of the implemented Advanced Surveillance Specimen Programme
Michal Kapusňák
2018
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Fracture Mechanics Uncertainty Analysis in the Reliability Assessment of the Reactor Pressure Vessel: (2D) Subjected to Internal Pressure
Mike Susmikanti
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA
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Analysis of warm prestressing effect on fracture toughness of reactor pressure vessel steels
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Strength of Materials, 2010
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Small punch test application for evaluation of the initial mechanical properties of VVER-440 / 213 type reactor pressure vessel materials
Michal Kapusňák
2017
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Improvement of the calculation of the stress intensity factors for underclad and through-clad defects in a reactor pressure vessel subjected to a pressurised thermal shock
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International Journal of Pressure Vessels and Piping, 2008
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Analysis of a reactor pressure vessel subjected to pressurized thermal shocks
M. Niffenegger
International Journal of Computational Methods and Experimental Measurements
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Summary of International PFM Round Robin analyses among Asian Countries on reactor pressure vessel integrity during pressurized thermal shock
Y. Kanto, Kuen Ting
International Journal of Pressure Vessels and Piping, 2012
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Characterisation of the fracture properties in the ductile to brittle transition region of the weld material of a reactor pressure vessel
Diego Ferreño
Journal of Nuclear Materials, 2011
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Stress intensity factors for underclad and through clad defects in a reactor pressure vessel submitted to a pressurised thermal shock
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International Journal of Pressure Vessels and Piping, 2005
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Integrity analysis of a reactor pressure vessel subjected to pressurized thermal shocks by considering constraint effect
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Engineering Fracture Mechanics, 2013
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Low cycle thermomechanical fatigue of VVER-440 reactor pressure vessel steels: Investigation the fatigue kinetics and development of a life assessment model
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Procedia Structural Integrity, 2016
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Contribution of multiscale materials modelling for underwriting nuclear pressure vessel integrity
Peter E J Flewitt
Materials Science and Technology, 2004
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DISTRIBUTIONS OF FABRICATION FLAWS IN REACTOR PRESSURE VESSELS FOR STRUCTURAL INTEGRITY EVALUATIONS
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On thermal annealing of irradiated PWR pressure vessels
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International Journal of Pressure Vessels and Piping, 1998
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