The SPACE (Safety and Performance Analysis Code) which is based on a multi-dimensional two-fluid, three-field model is under development for a licensing purpose of pressurized water reactors in Korea. A total of 12 wall-to-fluid heat transfer modes were defined and a heat transfer mode selection logic was developed according to the noncondensable gas quality, the void fraction, the degree of subcooling and the wall temperature. Among the constitutive equations of the SPACE code, post-CHF heat transfer models are considered to have the most significant uncertainties because their physical phenomena are not fully understood yet. Though a variety of models and correlations for the post-CHF heat transfer are available, there is no reliable model to reproduce the heat transfer rate as realistically as possible. Several post-CHF heat transfer models are implemented into the SPACE code; critical heat, transition and film boiling models. The present paper describes the model assessment progress which was done for the transition and film boiling models of the SPACE code. A heat flux partition into the continuous liquid, entrained droplet and vapor fields should be taken into account in order to be in line with physical phenomena as the SPACE code has three-field equations in its hydraulic solver. Existing energy partitioning methods were peer-reviewed in order to determine the best model which can be applicable to the SPACE code. The present work will help to consolidate the developed wall-to-fluid heat transfer package of the SPACE code.
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17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4353-6
PROCEEDINGS PAPER
Assessment of Post-CHF Heat Transfer Models for the SPACE Code Available to Purchase
K. Y. Choi,
K. Y. Choi
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
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B. J. Yun,
B. J. Yun
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
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H. S. Park,
H. S. Park
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
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S. K. Moon,
S. K. Moon
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
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K. D. Kim
K. D. Kim
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
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K. Y. Choi
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
B. J. Yun
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
H. S. Park
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
S. K. Moon
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
K. D. Kim
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
Paper No:
ICONE17-75178, pp. 205-214; 10 pages
Published Online:
February 25, 2010
Citation
Choi, KY, Yun, BJ, Park, HS, Moon, SK, & Kim, KD. "Assessment of Post-CHF Heat Transfer Models for the SPACE Code." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance. Brussels, Belgium. July 12–16, 2009. pp. 205-214. ASME. https://doi.org/10.1115/ICONE17-75178
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