Comparative RELAP5-3D analysis in support of the NPP DBA analysis in Ukraine (original) (raw)

Validation of RELAP5/MOD3.2 model of VVER440 on reactor scram transient

Pavlin Groudev

Progress in Nuclear Energy, 2006

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Simulation of a control rod ejection accident in a VVER-1000/V446 using RELAP5/Mod3.2

Kamal Hadad

Annals of Nuclear Energy, 2012

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Simulation of loss-of-flow transient in a VVER-1000nuclear power plant with RELAP5/MOD3.2

Pavlin Groudev

Progress in Nuclear Energy, 2004

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VALIDATION OF A RELAP5 COMPUTER MODEL FOR A VVER440/230V

Pavlin Groudev

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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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RELAP5/MOD3.3 Analysis of Reactor Trip Event in Nuclear Power Plant

Borut Mavko

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Comparison between RELAP5 Mod3.2 and Mod3.3 in Simulating a Large Break LOCA in Low Power Rrs

THE IJES Editor

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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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Performance Optimization and Validation for the PRHRS of VVERs with RELAP5 code

Huseyin Ayhan

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Analysis of the loss of heat sink transients in the secondary circuit of a VVER-1000 using RELAP5/MOD3.2

Kamal Hadad

Annals of Nuclear Energy, 2012

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Investigation of Critical Safety Function "Integrity" in Case of Steam Line Break Accident for Vver 1000/V320

Pavlin Groudev

2002

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ASTEC and ICARE/CATHARE modelling improvement for VVERs

Jean-pierre Van Dorsselaere

Nuclear Engineering and Design, 2011

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Modeling of control rod ejection transient for WWER-1000-model 446 using RELAP5m3.3/PARCSv2.6 coupled codes

masoud mansouri

Annals of Nuclear Energy, 2014

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Coupled 3-D kinetics thermal-hydraulic analysis of Hot Zero Power main steam line breaks using RETRAN and STAR codes

Madeline Feltus

Nuclear Engineering and Design, 1994

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Investigation of spatial coupling aspects for coupled code application in PWR safety analysis

Kostadin Ivanov

Annals of Nuclear Energy, 2003

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Evaluation of the RELAP5/SCDAP Accident Analysis Code Applicability to Candu Nuclear Reactors

Mirea Mladin

2009

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Loss of offsite power accident analysis in a VVER-1000/V446 nuclear power plant

Omar Gabrielli

Nuclear Technology and Radiation Protection, 2019

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Investigations of the VVER-1000 coolant transient benchmark phase 1 with the coupled system code RELAP5/PARCS

Víctor Hugo

Progress in Nuclear Energy, 2006

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RELAP5-3D code validation in the neutron-dynamic analysis of transient processes taking place in RBMK-1500 reactors

E. Uspuras

Nuclear Engineering and Design, 2003

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Validation of 3D neutronic-thermalhydraulic coupled codes RELAP5/PARCSv2.7 and TRACEv5.0P3/PARCSv3.0 against a PWR control rod drop transient

Teresa Barrachina

Journal of Nuclear Science and Technology, 2017

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HEMERA: a 3D computational chain for PWR safety analysis

Giovanni Bruna

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Simulation of VVER-1000 Guillotine Large Break Loss of Coolant Accident Using RELAP5/SCDAPSIM/MOD3.5

Fabiano Thulu

Journal of Nuclear Engineering, 2021

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Dynamic Model of the VVER-1000 Reactor for Seismic and LB LOCA Evaluation

Yaroslav Dubyk

Volume 4: Student Paper Competition, 2021

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Validation of RELAP5/MOD3.2 model on trip off one main coolant pump for VVER 440/V230

Pavlin Groudev

Nuclear Engineering and Design, 2006

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Validation of coupled neutron kinetic/thermal-hydraulic codes. Part 2: Analysis of a VVER-440 transient (Loviisa-1)

R. Kyrki-rajamäki

Annals of Nuclear Energy, 2002

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A COMPARISON OF SIMULATION ANALYSIS OF SAFETY SYSTEMS AND SEVERE ACCIDENT PROGRESSION FOR VVER-1200 AND AP-1000 FOLLOWING LOCA IN HOTLEG BY PCTRAN

Abdur Razzak, Md.Ghulam Zakir, Md. Sadman Anjum Joarder, Sushmita Barua

Proceedings of the International Conference on Mechanical Engineering and Renewable Energy 2021 (ICMERE 2021) 12 – 14 December 2021, Chattogram, Bangladesh., 2021

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Restructuring RELAP5- 3D for Next Generation Nuclear Plant Analysis American Nuclear Society 2006 Annual Meeting

Donna Guillen

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Validation of a RELAP5/MOD3.2 Computer Model on Actuation of Arpc for a VVER440/230V

Pavlin Groudev

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Validation of Coupled RELAP5-3D Code in the Analysis of RBMK-1500 Specific Transients

Algirdas Kaliatka

2003

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Quantitative assessment of MCP trip transient in a VVER

Boris Kvizda

Nuclear Engineering and Design, 2004

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