Hydrogen distribution in a nuclear reactor containment
DSpace at IIT Bombay
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Title |
Hydrogen distribution in a nuclear reactor containment
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Creator |
PRABHUDHARWADKAR, DM
IYER, KN MOHAN, N BAJAJ, SS MARKANDEYA, SG |
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Subject |
turbulence model
air-flow transport plumes |
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Description |
The management of hydrogen in nuclear reactor containment after LOCA is of practical importance to preserve the structural integrity of the containment. This paper presents the results of systematic work carried out using the commercial software FLUENT to assess the concentration distribution of hydrogen in a typical Indian Nuclear Reactor Containment. Accurate turbulence modelling is important to predict the concentration distribution correctly. The turbulence models which were most commonly cited in the literature for modelling buoyancy driven flows were assessed for their suitability and it was found that the buoyancy modified Standard k-epsilon model is adequate for the purpose by comparing with some experimental data available in the literature. Subsequently, unstructured meshes were generated to represent the containment of a typical Indian nuclear reactor. Analyses were carried Out to quantify the hydrogen distribution for three cases. These were (1) Uniform injection of hydrogen for a given period of time at room temperature, (2) Time varying injection as has been computed from an accident analysis code, (3) Time varying injection (as used in case (2)) at a high temperature. A parametric exercise was also carried Out in case (1) where the effect of various inlet orientations and locations on hydrogen distribution was studied. Results of all these cases have been presented in this paper.
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Publisher |
AMER SOC MECHANICAL ENGINEERS
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Date |
2011-10-26T02:44:13Z
2011-12-15T09:11:26Z 2011-10-26T02:44:13Z 2011-12-15T09:11:26Z 2008 |
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Type |
Proceedings Paper
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Identifier |
ICONE16: PROCEEDING OF THE 16TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2008, VOL 3,951-961
978-0-79184-816-6 http://dspace.library.iitb.ac.in/xmlui/handle/10054/15886 http://hdl.handle.net/100/2068 |
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Source |
16th International Conference on Nuclear Engineering,Orlando, FL,MAY 11-15, 2008
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Language |
English
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