Simulation of hydrogen deflagration experiment – Benchmark exercise with lumped-parameter codes

Kljenak, Ivo; Kuznetsov, M.; Kostka, P.; Kubisova, L.; Maltsev, M.B.; Manzini, G.; Povilaitis, Mantas

doi:10.1016/j.nucengdes.2014.07.016

Cited by 8 publications

(3 citation statements)

References 7 publications

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“…The IBE-3 reached conclusions that can help further investigations on hydrogen distribution. However, as with other benchmarks in the literature (Gallego et al, 2007;Kljenak et al, 2015), it was difficult to draw general conclusions from one participant to another because of the different mesh, solver or physics.…”

Section: Introductionmentioning

confidence: 99%

Analysis of a gas stratification break-up by a vertical jet using the GOTHIC code

Fernández-Cosials

Varas

López-Alonso

2016

Nuclear Engineering and Design

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Section: Introductionmentioning

confidence: 99%

Analysis of a gas stratification break-up by a vertical jet using the GOTHIC code

Fernández-Cosials

Varas

López-Alonso

2016

Nuclear Engineering and Design

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“…The program COCOSYS, a lumped-parameter code, is being developed by the Gesellschaft für Anlagen-und Reaktorsicherheit (GRS) gGmbH, Germany, for the simulation of all relevant processes and plant states during severe accidents in containment of light water reactors. And this code is widely used in nuclear engineering [8,9]. The characteristic feature of lumped-parameter approach is that mass and energy are transferred between control volumes by junctions, according to momentum equation solution for each junction.…”

Section: Introductionmentioning

confidence: 99%

Assessment of Prediction Capabilities of COCOSYS and CFX Code for Simplified Containment

Zhu

Zhang

2016

Science and Technology of Nuclear Installations

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The acceptable accuracy for simulation of severe accident scenarios in containments of nuclear power plants is required to investigate the consequences of severe accidents and effectiveness of potential counter measures. For this purpose, the actual capability of CFX tool and COCOSYS code is assessed in prototypical geometries for simplified physical process-plume (due to a heat source) under adiabatic and convection boundary condition, respectively. Results of the comparison under adiabatic boundary condition show that good agreement is obtained among the analytical solution, COCOSYS prediction, and CFX prediction for zone temperature. The general trend of the temperature distribution along the vertical direction predicted by COCOSYS agrees with the CFX prediction except in dome, and this phenomenon is predicted well by CFX and failed to be reproduced by COCOSYS. Both COCOSYS and CFX indicate that there is no temperature stratification inside dome. CFX prediction shows that temperature stratification area occurs beneath the dome and away from the heat source. Temperature stratification area under adiabatic boundary condition is bigger than that under convection boundary condition. The results indicate that the average temperature inside containment predicted with COCOSYS model is overestimated under adiabatic boundary condition, while it is underestimated under convection boundary condition compared to CFX prediction.

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“…The IBE-3 reached conclusions that can help further investigations on hydrogen distribution. However, as with other benchmarks in the literature like Gallego's or Klejnak, [119,120], it was difficult to draw general conclusions from one participant to another because of the different mesh, solver, simulation settings or physics.…”

Section: Hydrogen Ignitionmentioning

confidence: 99%

Analysis and improvement of hydrogen mitigation strategies during a severe accident in nuclear containments

Fernández-Cosials¹

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Simulation of hydrogen deflagration experiment – Benchmark exercise with lumped-parameter codes

Cited by 8 publications

References 7 publications

Analysis of a gas stratification break-up by a vertical jet using the GOTHIC code

Analysis of a gas stratification break-up by a vertical jet using the GOTHIC code

Assessment of Prediction Capabilities of COCOSYS and CFX Code for Simplified Containment

Analysis and improvement of hydrogen mitigation strategies during a severe accident in nuclear containments

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