Assessment of reactor vessel integrity (ARVI) (original) (raw)
Plant application of ICARE/ASTECv2.0r3 computer code for investigation of in-vessel melt retention in VVER-1000 reactor design
Pavlin Groudev
Annals of Nuclear Energy, 2015
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In-Vessel Melt Retention (IVMR) Analysis of a VVER-1000 NPP
Ladislav Vyskočil
2016
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Some considerations to improve the methodology to assess In-Vessel Retention strategy for high-power reactors
J. Zdarek, Florian Fichot
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Methodological developments in the field of structural integrity analyses of large scale reactor pressure vessels in Hungary
Tamas Fekete
Frattura ed Integrità Strutturale, 2016
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Coupled thermo-mechanical creep analysis for boiling water reactor pressure vessel lower head
walter villanueva
Nuclear Engineering and Design
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Evaluation of VVER-1200/V-491 Reactor Pressure Vessel integrity during large break LOCA along with SBO using MELCOR 1.8.6
Willard Mwemba
Nuclear Science and Technology, 2015
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Assessment of the possibility of core melt containment in a BBER-640 vessel
I. Likhachev
Atomic Energy, 1996
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On the validation and application of fluid–structure interaction analysis of reactor vessel internals at loss of coolants accidents
Jan Sundqvist
Computers & Structures, 2003
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Investigation of the pressure vessel lower head potential failure under IVR-ERVC condition during a severe accident scenario in APR1400 reactors
Yacine Addad, Muritala A Amidu
Nuclear Engineering and Design
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Creep failure of a reactor pressure vessel lower head under severe accident conditions
Martin Pilch
1998
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Modelling of Severe Accident and In-Vessel Melt Retention Possibilities in BWR Type Reactor
Algirdas Kaliatka
Science and Technology of Nuclear Installations, 2018
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Scaled Vessel Failure Experiment Analysis and Investigation of a Possible Vessel Support
H. Willschütz
Jahrestagung Kerntechnik, 2002
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Demonstration of Structural Integrity of Boiling Water Reactor Pressure Vessels Under Ultimate Response Guideline Operation
Yuh-ming Ferng
Nuclear Technology, 2020
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Integrity Evaluation of a Reactor Pressure Vessel Based on a Sequential Abaqus-FRANC3D Simulation Method
M. Annor-nyarko
Science and Technology of Nuclear Installations, 2021
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Investigation of IVMR Strategy with External Vessel Bottom Head Water Cooling in VVER 1000 / v 320 Reactor Design with ASTECv 2 . 1 . 0 . 3 Computer Code
A. Stefanova
2016
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LIVE Experiments on Melt Behavior in the Reactor Pressure Vessel Lower Head
Major Major
Heat Transfer Engineering, 2013
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Reactor Safety Gap Evaluation of Accident Tolerant Components and Severe Accident Analysis
Randall Gauntt
2015
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Evaluation of heat-flux distribution at the inner and outer reactor vessel walls under the in-vessel retention through external reactor vessel cooling condition
Sang Ho An
Nuclear Engineering and Technology, 2015
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The accumulator effects on in-vessel severe accident progression of a three loop PWR nuclear power plant in a SBLOCA without safety injection system
mohsen Shayesteh
Annals of Nuclear Energy, 2017
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PERFECT – Prediction of Irradiation Damage Effects on Reactor Components: A summary
Stéphane Bugat
Journal of Nuclear Materials, 2010
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Thermal Hydraulic Analysis in Reactor Vessel Internals Considering Irradiation Heat
Kunwoo Yi
2015
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Fracture mechanical evaluation of an in-vessel melt retention scenario
H. Willschütz
Annals of Nuclear Energy, 2008
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Safety Related Investigations of the VVER-1000 Reactor Type by the Coupled Code System TRACE/PARCS
Victor Hugo Sanchez Espinoza
Journal of Power and Energy Systems, 2008
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Study of in-vessel melt retention for VVER-1000/v320 reactor
Pavlin Groudev
Nuclear Engineering and Design, 2016
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High Temperature Thermal and Structural Material Properties for Metals Used in LWR Vessels
John Crepeau
2008
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Experimental study of the fracture kinetics of a tubular 16MnNiMo5 steel specimen under biaxial loading at 900 and 1000°C. Application to the rupture of a vessel bottom head during a core meltdown accident in a pressurized water reactor
A. Combescure, N. Tardif
Nuclear Engineering and Design, 2011
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Thermal expansion coefficient of steels used in LWR vessels
John Crepeau
Journal of Nuclear Materials, 2008
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ICONE15-10438 Safety Related Investigations of the VVER-1000 Reactor Type by the Coupled Code System Trace/Parcs
Victor Hugo Sanchez Espinoza
The Proceedings of the International Conference on Nuclear Engineering (ICONE), 2007
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Views on R&D needs about in-vessel reflooding issues, with a focus on debris coolability
Jean-pierre Van Dorsselaere
Nuclear Engineering and Design, 2006
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Assessment of S/R5/Mod3.3 Model of Stratified Molten Pool and Debris-To-Vessel Contact Resistence by TMI-2 Lower Head Creep Rupture Analyses. Nuclear Technology Vol. 156, NO. 2, P. 191-212
Sang Lung Chan
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Influence of the depth position on the neutron embrittlement of the VVER reactor pressure vessel steel 15Cr2MoV(A) consequences for the assessment of reactor safety
Mirco Große
Nuclear Engineering and Design, 1995
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DISTRIBUTIONS OF FABRICATION FLAWS IN REACTOR PRESSURE VESSELS FOR STRUCTURAL INTEGRITY EVALUATIONS
Abhinav Ojha
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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
Dagmar Jandova
Procedia Structural Integrity, 2016
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