The Generic Containment SB-LOCA accident simulation: Comparison of the parameter uncertainties and user-effect

Povilaitis, Mantas; Kelm, Stephan; Urbonavičius, E.

doi:10.1016/j.anucene.2017.03.037

Cited by 3 publications

(1 citation statement)

References 3 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…This code is suitable for safety analysis of nuclear power plant containment buildings [11]. Recently, an interesting study by Povilaitis et al [12] about the uncertainty and sensitivity analysis for a generic containment severe accident has demonstrated that both user effects and input uncertainties play a similar role. In the review by De Boeck [13], the author has described the main threats to the containment integrity and the state of knowledge and remaining uncertainties.…”

Section: A Specific Type Of Large Break Loss Of Coolant Accident (Lb-mentioning

confidence: 99%

Simulation of hydrogen distribution and effect of Engineering Safety Features (ESFs) on its mitigation in a WWER-1000 containment

et al. 2019

View full text Add to dashboard Cite

In this study, thermal-hydraulic parameters inside the containment of WWER-1000/v446 nuclear power plant are simulated in a Double Ended Cold Leg (DECL) accident for short and long times (by using CONTAIN 2.0 and MELCOR 1.8.6 codes) and the effect of the spray system as an Engineering Safety Feature (ESF) on parameters mitigation are analyzed with the former code. Along with the development of the accident from Design Basis Accident (DBA) to Beyond Design Basis Accident (BDBA), the zircaloy-steam reaction becomes the source of in-vessel hydrogen generation. Hydrogen distribution inside the containment is simulated for long time (using CONTAIN and MELCOR) and the effect of recombiners on its mitigation are analyzed (using MELCOR). Thermal-hydraulic parameters and hydrogen distribution profiles are presented as the outcome of the investigation. By activating the spray system, the peak points of pressure and temperature occur in the short time and remain below the maximum design values along the accident time. It is also shown that recombiners have a reliable effect on reducing the hydrogen concentration below flame-propagation limit in the accident localization area. The parameters predicted by CONTAIN and MELCOR are in good agreement with the Final Safety Analysis Report. The noted discrepancies are discussed and explained.

show abstract

Section: A Specific Type Of Large Break Loss Of Coolant Accident (Lb-mentioning

confidence: 99%

Simulation of hydrogen distribution and effect of Engineering Safety Features (ESFs) on its mitigation in a WWER-1000 containment

et al. 2019

View full text Add to dashboard Cite

show abstract

COCOSYS analysis on aerosol wash-down of THAI-AW3 experiment and generic containment

Wang

Gupta

2021

Annals of Nuclear Energy

View full text Add to dashboard Cite

Analysis of depressurization ability for IRIS containment during SBLOCAs using RELAP5 and CONTEMPT

Huang

Peng²,

Liu³

2023

Annals of Nuclear Energy

View full text Add to dashboard Cite

The Generic Containment SB-LOCA accident simulation: Comparison of the parameter uncertainties and user-effect

Cited by 3 publications

References 3 publications

Simulation of hydrogen distribution and effect of Engineering Safety Features (ESFs) on its mitigation in a WWER-1000 containment

Simulation of hydrogen distribution and effect of Engineering Safety Features (ESFs) on its mitigation in a WWER-1000 containment

COCOSYS analysis on aerosol wash-down of THAI-AW3 experiment and generic containment

Analysis of depressurization ability for IRIS containment during SBLOCAs using RELAP5 and CONTEMPT

Contact Info

Product

Resources

About