Pressure and temperature analyses using GOTHIC for Mark I containment of the Chinshan Nuclear Power Plant

Chen, Yen-Shu; Yuann, Yng-Ruey; Dai, Liang-Che; Lin, Yon-Pon

doi:10.1016/j.nucengdes.2011.02.004

Cited by 24 publications

(7 citation statements)

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“…To decide which tools are more appropriate for this task, the technical reports from the OECD/NEA have provided an exhaustive overview on the main simulation tools for hydrogen risk problems (NEA, 1999(NEA, , 2015. The use of 3D containment codes has been widely extended for detailed containment mass and energy release simulations throughout the last years (Chen et al, 2011(Chen et al, , 2012Papini et al, 2011;Jimenez et al, 2015;Ozdemir et al, 2015a;Bocanegra et al, 2016;Xiao et al, 2016). In the named NEA reports, the use of a suite of tools such as a combination of a lumped parameter code, like MELCOR or MAAP, with a 3D containment code, like GOTHIC or GASFLOW, is highly recommended for hydro gen risk mitigation analysis.…”

Section: Introductionmentioning

confidence: 99%

Hydrogen distribution and Passive Autocatalytic Recombiner (PAR) mitigation in a PWR-KWU containment type

López-Alonso

Papini

Varas

2017

Annals of Nuclear Energy

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The evaluation of Passive Autocatalytic Recombiners (PARs) performance has been foreseen from the EU stress tests in the frarnework of a complementary and comprehensive review of the safety of the Nuclear Power Plants (NPPs).The study presented in this work analyses the size,location and number of the PARs to minimise the risk arising from a hydrogen release and its distribution in the containment building dur ing a hypothetical severe accident A detailed 30 rnodel of a PWR KWU containment type was used for the simulations.The numerical tool is the GOTHIC 8.1 containrnent code, which can model certain aspects of the system geometry and beha viour in more detail than typically considered in containment performance analysis.The severe accident scenario chosen is a fast release of hydrogen steam mixture from hot leg creep rupture during SBO (Station Black Out) accident. In the first place, the hydrogen preferential pathways and points of hydrogen accumulation were studied and identified starting from the base case scenario without any mitigation measure. Secondly, a con figuration of PARs was simulated under the same conditions ofthe unmitigated case.The number of PARs considered is 40 units distributed all over the containrnent building. The PAR configuration offered an improvement in the chosen accidental scenario, decreasing the pos sibility of hydrogen combustion in all the containment compartrnents at the end of the transient The analyses showed that this PAR configuration could lead toa reduction between 30 45% of the final hydro gen concentration.The hydrogen combustion risk is decreased with final hydrogen concentration values below the flamrnability limit (hydrogen concentration below 7%). Nonetheless, the analysis showed the inability of the PARs to recombine in the early stage of the fast release (the first 1 2min in this sequence), due to their inertia and occurrence of oxygen starvation conditions.

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Section: Introductionmentioning

confidence: 99%

Hydrogen distribution and Passive Autocatalytic Recombiner (PAR) mitigation in a PWR-KWU containment type

López-Alonso

Papini

Varas

2017

Annals of Nuclear Energy

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“…Douglass et al (2009) used GOTHIC to perform short-term ABWR analyses of the South Texas Project units 3 and 4. The authors also have used GOTHIC to analyze the containment pressure responses of the Mark I (Chen et al, 2011), Mark III (Lin et al, 2013), and ABWR (Chen et al, 2012) plants. Furthermore, the multi-dimensional model of GOTHIC can be applied to investigate the pool or gas mixing in the containments.…”

Section: Introductionmentioning

confidence: 99%

Negative pressure difference evaluation of Lungmen ABWR containment by using GOTHIC

Chen

Yuann

2015

Annals of Nuclear Energy

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“…It has been verified and validated by previous experimental data. Besides, GOTHIC has been applied to many applications in recent years (Andreanit et al, 2011;Papini et al, 2011;Kim and Park, 2011;Chen et al, 2011). Fig.…”

Section: Introductionmentioning

confidence: 99%

Kuosheng Mark III containment analyses using GOTHIC

Lin

Chen

Yuann

2013

Nuclear Engineering and Design

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Pressure and temperature analyses using GOTHIC for Mark I containment of the Chinshan Nuclear Power Plant

Cited by 24 publications

References 1 publication

Hydrogen distribution and Passive Autocatalytic Recombiner (PAR) mitigation in a PWR-KWU containment type

Hydrogen distribution and Passive Autocatalytic Recombiner (PAR) mitigation in a PWR-KWU containment type

Negative pressure difference evaluation of Lungmen ABWR containment by using GOTHIC

Kuosheng Mark III containment analyses using GOTHIC

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