Analysis of cold leg LOCA with failed HPSI by means of integrated safety assessment methodology
J Gonzalez-Cadelo, C Queral… - Annals of Nuclear …, 2014 - Elsevier
The integrated safety assessment (ISA) methodology, developed by the Spanish Nuclear
Safety Council (CSN), has been applied to a thermal–hydraulic analysis of cold leg LOCA …
Safety Council (CSN), has been applied to a thermal–hydraulic analysis of cold leg LOCA …
Effects of delayed RCP trip during SBLOCA in PWR
J Montero-Mayorga, C Queral… - Annals of Nuclear …, 2014 - Elsevier
Abstract After the Three Mile Island (TMI) accident, the issue of when to trip the Reactor
Coolant Pumps (RCPs) in case of a Small Break Loss of Coolant Accident (SBLOCA) …
Coolant Pumps (RCPs) in case of a Small Break Loss of Coolant Accident (SBLOCA) …
Activities in Spain on the integration of probabilistic and deterministic safety analysis methods. Discussion on their applicability to DEC-A scenarios
This paper presents a summary of theoretical and applied achievements in the field of
integrated methods of nuclear safety analysis produced by Spain's nuclear safety …
integrated methods of nuclear safety analysis produced by Spain's nuclear safety …
AP1000® SBLOCA simulations with TRACE code
J Montero-Mayorga, C Queral… - Annals of Nuclear …, 2015 - Elsevier
The AP1000® is an advanced pressurized water reactor (PWR) design developed by
Westinghouse which implements passive safety systems to provide core cooling in case of …
Westinghouse which implements passive safety systems to provide core cooling in case of …
Verification of SAMGs in SBO sequences with Seal LOCA. Multiple damage domains
Abstract The Integrated Safety Assessment (ISA) methodology, developed by the Spanish
Nuclear Safety Council, has been applied to PWR Station Blackout (SBO) sequences in the …
Nuclear Safety Council, has been applied to PWR Station Blackout (SBO) sequences in the …
Effect of a boric acid corrosive environment on the microstructure and properties of concrete
Y Wang, B Huang, Z Mao, M Deng, H Cao - Materials, 2020 - mdpi.com
Boric acid, a weak acid, is often used to shield neutrons in water cooling systems in nuclear
power stations. The leakage of boric acid in water cooling systems damages the concrete …
power stations. The leakage of boric acid in water cooling systems damages the concrete …
Evaluation of the offsite dose contribution to the global risk in a Steam Generator Tube Rupture scenario
The current main figure of merit for risk based decision making process based on
Probabilistic Safety Assessment level 1 is usually related with the fuel failure (ie, Peak …
Probabilistic Safety Assessment level 1 is usually related with the fuel failure (ie, Peak …
Management of the SBLOCA sequences with HPIS failure in VVER-1000/V320 reactors; comparison with Westinghouse PWR strategies
E Redondo-Valero, C Queral… - Progress in Nuclear …, 2024 - Elsevier
In small break LOCA sequences with failure of the high-pressure safety injection system, the
reactor coolant system pressure can stagnate at a high value making the medium and low …
reactor coolant system pressure can stagnate at a high value making the medium and low …
[HTML][HTML] ROSA/LSTF test and RELAP5 code analyses on PWR 1% vessel upper head small-break LOCA with accident management measure based on core exit …
T Takeda - Nuclear Engineering and Technology, 2018 - Elsevier
An experiment was performed using the large-scale test facility (LSTF), which simulated a
1% vessel upper head small-break loss-of-coolant accident with an accident management …
1% vessel upper head small-break loss-of-coolant accident with an accident management …
Assessment of safety injection in severe accident management following BDBA scenarios in a Swedish PWR
Analytical simulation using best-estimate codes were suggested to be extended for the
elaboration and improvement of SAMG in current PWRs. This work is about to perform an …
elaboration and improvement of SAMG in current PWRs. This work is about to perform an …