Development of a hydrogen diffusion gothic model of MARK III-containment
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H. Zhen-Yu
Abstract
The accident that occurred at the Fukushima Daiichi Nuclear Power Plant is a reminder of the danger of hydrogen explosion within a reactor building. Sufficiently high hydrogen concentration may cause an explosion that could damage the structure, resulting in the release of radioisotopes into the environment. In the first part of this study, a gas diffusion experiment was performed, in which helium was used as the working fluid. An analytical model was also developed using the GOTHIC code and the model predictions of the helium distribution were found to be in good agreement with the experimentally measured data. In the second part of the study, a model of the Mark III containment of the Kuosheng Plant in Taiwan was developed, and was applied to a long-term station blackout (SBO) accident similar to that of the Fukushima plant. The hydrogen generation was calculated using the Modular Accident Analysis Program and was used as the boundary condition for the GOTHIC containment model. The simulation results revealed that the hydrogen concentration at the first floor of the wetwell in the containment reached 4% 9.7 h after the accident. This indicated the possibility of dangerous conditions inside the containment. Although active hydrogen ignitors are already installed in the Kuosheng plant, the findings of this study indicate that it may be necessary to add passive recombiners to prolong an SBO event.
Kurzfassung
Der Unfall im Kernkraftwerk Fukushima Daiichi ist eine Erinnerung an die Gefahren einer Wasserstoffexplosion im Innern eines Reaktorgebäudes. Eine ausreichend hohe Wasserstoffkonzentration kann eine Explosion bewirken, die die Gebäudestruktur beschädigt und zu einer Freisetzung von Radionukliden in die Umwelt führt. Im ersten Teil dieser Studie wurde ein Gasdiffusionsexperiment durchgeführt bei dem Helium als Arbeitsmedium verwendet wurde. Ein analytisches Modell wurde mit Hilfe des GOTHIC-Code entwickelt und die Modellvorhersagen der Heliumverteilung befanden sich in guter Übereinstimmung mit den experimentell gemessenen Daten. Im zweiten Teil der Studie wurde ein Model des Mark III-Containments des Kuosheng-Kernkraftwerks in Taiwan entwickelt und auf einen Langzeitausfallunfall (SBO) ähnlich dem in der Fukushima Anlage angewendet. Die Wasserstofferzeugung wurde mit Hilfe des Modular Accident Analysis-Programms berechnet und als Randbedingung für das GOTHIC-Containment-Modell verwendet. Die Simulationsergebnissse zeigen, dass die Wasserstoffkonzentration im Containment 9.7 h nach dem Unfall 4% erreicht. Dies weist auf die Möglichkeit gefährlicher Bedingungen im Containment hin. Obwohl bereits aktive Wasserstoff-Zündeinrichtungen in der Kuosheng-Anlage installiert sind, zeigen die Ergebnisse dieser Studie, dass es nötig sein könnte zusätzlich passive Rekombinatoren zu installieren.
References
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© 2015, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Improved data evaluation methodology for energy ranges with missing experimental data
- Importance weighting of local flux measurements to improve reactivity predictions in nuclear systems
- Safety assessment of fuel cycle facilities following the lessons learned from the accident at the Fukushima-Daiichi nuclear power plant
- The ultimate response guideline simulation and analysis by using TRACE for Lungmen ABWR nuclear power plant
- Development of a hydrogen diffusion gothic model of MARK III-containment
- Analysis of safety parameters for the MINERVE reactor
- Nondestructive radioactive tracer technique in performance evaluation of organic based ion exchange materials Purolite NRW-4000 and Duolite A-378
- Neutronic performance of (ReprocessedU/Th)O2 fuel in CANDU 6 reactor
- Modelling study on production cross sections of 111In radioisotopes used in nuclear medicine
- Study of 60Co as gamma source in backscatter gamma densitometers
- Determination of activity concentration of natural and artificial radionuclides in sand samples from mediterranean coast of Antalya in Turkey
- Technical Notes
- Numerical solution of diffusion equation to study fast neutrons flux distribution for variant radii of nuclear fuel pin and moderator regions
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Improved data evaluation methodology for energy ranges with missing experimental data
- Importance weighting of local flux measurements to improve reactivity predictions in nuclear systems
- Safety assessment of fuel cycle facilities following the lessons learned from the accident at the Fukushima-Daiichi nuclear power plant
- The ultimate response guideline simulation and analysis by using TRACE for Lungmen ABWR nuclear power plant
- Development of a hydrogen diffusion gothic model of MARK III-containment
- Analysis of safety parameters for the MINERVE reactor
- Nondestructive radioactive tracer technique in performance evaluation of organic based ion exchange materials Purolite NRW-4000 and Duolite A-378
- Neutronic performance of (ReprocessedU/Th)O2 fuel in CANDU 6 reactor
- Modelling study on production cross sections of 111In radioisotopes used in nuclear medicine
- Study of 60Co as gamma source in backscatter gamma densitometers
- Determination of activity concentration of natural and artificial radionuclides in sand samples from mediterranean coast of Antalya in Turkey
- Technical Notes
- Numerical solution of diffusion equation to study fast neutrons flux distribution for variant radii of nuclear fuel pin and moderator regions
