Fukushima Daiichi Unit 1 power plant containment analysis using GOTHIC

Özdemir, Ö.; George, Thomas; Marshall, Mervin D.

doi:10.1016/j.anucene.2015.06.017

Cited by 20 publications

(5 citation statements)

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“…A large validation effort against light gas experiments has been performed with 2D and 3D models, as can be seen in (Andreani et al, 2012(Andreani et al, , 2010Hultgren et al, 2014;Paladino et al, 2010). Recent applications of GOTHIC 3D models involve research on hydrogen safety (Fernández-Cosials et al, 2017), steam discharges into a pool (Estévez-Albuja et al, 2018;Gallego-Marcos et al, 2018), filtered containment venting systems (Fernández-Cosials et al, 2018), depressurization transients in the High Temperature Gas Reactor (HTGR) (Yildiz et al, 2018), or the Fukushima accident analysis (Ozdemir et al, 2015). The code version used in the present study is GOTHIC 8.2 QA (EPRI, 2016b).…”

Section: The Gothic Codementioning

confidence: 99%

3D containment modeling of PWR-KWU Trillo NPP with the GOTHIC code

Fernández-Cosials

Estévez-Albuja

Varas

et al. 2019

Annals of Nuclear Energy

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Containment safety analysis is a field in expansion given the complex phenomenology developed during an accident, and the recent code capabilities improvement. In this paper, a modeling strategy to create complex containments with porous CFDs in a single control volume is presented. This methodology involves using solely Computer Aided Design (CAD) tools, to manage the geometrical model, instead of using the GOTHIC code pre-processor interface. This methodology is applied to Trillo NPP (KWU 3 loops) where a LBLOCA is simulated to illustrate its capabilities. The results are compared against a Lumped Parameters model obtaining similar average values. Finally, a sensitivity analysis is made to quantify the influence of the modeling simplifications showing a small dependence. This implies that this modeling strategy is able to recreate models accurately, with an affordable computational cost, and with a time saving improvement, which nowadays is the main bottleneck for 3D containment models.

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Section: The Gothic Codementioning

confidence: 99%

3D containment modeling of PWR-KWU Trillo NPP with the GOTHIC code

Fernández-Cosials

Estévez-Albuja

Varas

et al. 2019

Annals of Nuclear Energy

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“…Typically, there are two kinds of computational codes used for system thermal-hydraulic analysis: system codes (e.g., RELAP, TRACE) that describe the reactor system as a network of simple control volumes connected with junctions and computational fluid dynamics (CFD)-like codes (e.g., GOTHIC) that provide a three-dimensional (3D) simulation capability using coarse-mesh configurations with the sub-grid phenomena in boundary layer that is well captured by adequate constitutive correlations (e.g., wall functions and turbulence models). Compared with standard system codes (with much loss of local information) and standard fine-mesh CFD codes (with huge computational cost), these coarse-mesh, CFD-like codes have natural advantages and have been widely used to achieve sufficient accuracy for long-term thermal-hydraulic simulation of multicomponent system (Chen et al, 2011, Ozdemir, George & Marshall, 2015, Bao et al, 2016, Bao et al, 2018b. They solve the conservation equations for mass, momentum, and energy for multicomponent multiphase flow.…”

Section: Introductionmentioning

confidence: 99%

Using deep learning to explore local physical similarity for global-scale bridging in thermal-hydraulic simulation

Bao

Dinh

Lin

et al. 2020

Annals of Nuclear Energy

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“…Mass and energy sources are obtained using the MAAP code and a 3D GOTHIC containment model is used for predicting the hydrogen distribution. The NAI Company (developers of GOTHIC) performed an extensive analysis of the Fukushima I accident using MAAP5 as the source code and GOTHIC as the code to simulate the detailed response of the containment (Ozdemir et al, 2015b).…”

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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Fukushima Daiichi Unit 1 power plant containment analysis using GOTHIC

Cited by 20 publications

References 0 publications

3D containment modeling of PWR-KWU Trillo NPP with the GOTHIC code

3D containment modeling of PWR-KWU Trillo NPP with the GOTHIC code

Using deep learning to explore local physical similarity for global-scale bridging in thermal-hydraulic simulation

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

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