Application of the integrated safety assessment methodology to safety margins. Dynamic event trees, damage domains and risk assessment
Abstract The Integrated Safety Assessment (ISA) methodology, developed by the Consejo
de Seguridad Nuclear, has been applied to an analysis of Zion NPP for sequences with …
de Seguridad Nuclear, has been applied to an analysis of Zion NPP for sequences with …
Dynamic event trees without success criteria for full spectrum LOCA sequences applying the integrated safety assessment (ISA) methodology
C Queral, J Gómez-Magán, C París… - Reliability Engineering & …, 2018 - Elsevier
The integrated safety assessment (ISA) methodology, developed by the Spanish nuclear
safety council (CSN), has been applied to the analysis of full spectrum loss of coolant …
safety council (CSN), has been applied to the analysis of full spectrum loss of coolant …
Effectiveness of the debris bed self-leveling under severe accident conditions
S Basso, A Konovalenko, P Kudinov - Annals of Nuclear Energy, 2016 - Elsevier
Melt fragmentation, quenching and long term coolability in a deep pool of water under the
reactor vessel are employed as a severe accident mitigation strategy in several designs of …
reactor vessel are employed as a severe accident mitigation strategy in several designs of …
Failure domain analysis and uncertainty quantification using surrogate models for steam explosion in a Nordic type BWR
D Grishchenko, S Galushin, P Kudinov - Nuclear Engineering and Design, 2019 - Elsevier
Sever accident mitigation strategy adopted in Nordic Boiling Water Reactors (BWRs)
employs a deep water pool below the reactor vessel to fragment and quench core melt and …
employs a deep water pool below the reactor vessel to fragment and quench core melt and …
Prediction of in-vessel debris bed properties in BWR severe accident scenarios using MELCOR and neural networks
VA Phung, D Grishchenko, S Galushin… - Annals of Nuclear …, 2018 - Elsevier
Severe accident management strategy in Nordic boiling water reactors (BWRs) employs ex-
vessel corium debris coolability. In-vessel core degradation and relocation provide initial …
vessel corium debris coolability. In-vessel core degradation and relocation provide initial …
Characteristics of debris in the lower head of a BWR in different severe accident scenarios
VA Phung, S Galushin, S Raub, A Goronovski… - … Engineering and Design, 2016 - Elsevier
Nordic boiling water reactors (BWRs) adopt ex-vessel debris cooling to terminate severe
accident progression. Core melt released from the vessel into a deep pool of water is …
accident progression. Core melt released from the vessel into a deep pool of water is …
[PDF][PDF] Comparison of MELCOR and MAAP calculations of core relocation phenomena in Nordic BWR´ s
A Tuvelid - 2016 - diva-portal.org
Since the crisis in Fukushima, severe accident progression during a station blackout (SBO)
accident is recognized as a very important area for accident management and emergency …
accident is recognized as a very important area for accident management and emergency …
Development of risk oriented accident analysis methodology (ROAAM+) for assessment of ex-vessel severe accident management effectiveness
P Kudinov, S Galushin, D Grishchenko… - 18th International Topical …, 2019 - elibrary.ru
In this work we present results of development and application of Risk Oriented Accident
Analysis framework (ROAAM+) to assessment of effectiveness of ex-vessel severe accident …
Analysis framework (ROAAM+) to assessment of effectiveness of ex-vessel severe accident …
Input Calibration, Code Validation and Surrogate Model Development for Analysis of Two-phase Circulation Instability and Core Relocation Phenomena
VA Phung - 2017 - diva-portal.org
Code validation and uncertainty quantification are important tasks in nuclear reactor safety
analysis. Code users have to deal with large number of uncertain parameters, complex multi …
analysis. Code users have to deal with large number of uncertain parameters, complex multi …