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Title: The developments and verifications of trace model for IIST LOCA experiments

Abstract

The test facility IIST (INER Integral System Test) is a Reduced-Height and Reduced-Pressure (RHRP) integral test loop, which was constructed for the purposes of conducting thermal hydraulic and safety analysis of the Westinghouse three-loop PWR Nuclear Power Plants. The main purpose of this study is to develop and verify TRACE models of IIST through the IIST small break loss of coolant accident (SBLOCA) experiments. First, two different IIST TRACE models which include a pipe-vessel model and a 3-D vessel component model have been built. The steady state and transient calculation results show that both TRACE models have the ability to simulate the related IIST experiments. Comparing with IIST SBLOCA experiment data, the 3-D vessel component model has shown better simulation capabilities so that it has been chosen for all further thermal hydraulic studies. The second step is the sensitivity studies of two phase multiplier and subcooled liquid multiplier in choked flow model; and two correlation constants in CCFL model respectively. As a result, an appropriate set of multipliers and constants can be determined. In summary, a verified IIST TRACE model with 3D vessel component, and fine-tuned choked flow model and CCFL model is established for further studies on IIST experimentsmore » in the future. (authors)« less

Authors:
 [1]; ;  [2]; ;  [1]
  1. Inst. of Nuclear Engineering and Science, National Tsing-Hua Univ., Taiwan, No. 101, Kuang-Fu Road, Hsinchu 30013, Taiwan (China)
  2. Inst. of Nuclear Energy Research, Taiwan, No. 1000, Wenhua Rd., Longtan Township, Taoyuan County 32546, Taiwan (China)
Publication Date:
Research Org.:
American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
OSTI Identifier:
22107789
Resource Type:
Conference
Resource Relation:
Conference: ICAPP '12: 2012 International Congress on Advances in Nuclear Power Plants, Chicago, IL (United States), 24-28 Jun 2012; Other Information: Country of input: France; 6 refs.; Related Information: In: Proceedings of the 2012 International Congress on Advances in Nuclear Power Plants - ICAPP '12| 2799 p.
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; COMPUTER GRAPHICS; CONTAINERS; FLOW MODELS; LIQUIDS; LOSS OF COOLANT; PWR TYPE REACTORS; SAFETY ANALYSIS; SENSITIVITY ANALYSIS; SIMULATION; STEADY-STATE CONDITIONS; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS

Citation Formats

Zhuang, W. X., Wang, J. R., Lin, H. T., Shih, C., Huang, K. C., and Dept. of Engineering and System Science, National Tsing-Hua Univ., Taiwan, No. 101, Kuang-Fu Road, Hsinchu 30013, Taiwan. The developments and verifications of trace model for IIST LOCA experiments. United States: N. p., 2012. Web.
Zhuang, W. X., Wang, J. R., Lin, H. T., Shih, C., Huang, K. C., & Dept. of Engineering and System Science, National Tsing-Hua Univ., Taiwan, No. 101, Kuang-Fu Road, Hsinchu 30013, Taiwan. The developments and verifications of trace model for IIST LOCA experiments. United States.
Zhuang, W. X., Wang, J. R., Lin, H. T., Shih, C., Huang, K. C., and Dept. of Engineering and System Science, National Tsing-Hua Univ., Taiwan, No. 101, Kuang-Fu Road, Hsinchu 30013, Taiwan. 2012. "The developments and verifications of trace model for IIST LOCA experiments". United States.
@article{osti_22107789,
title = {The developments and verifications of trace model for IIST LOCA experiments},
author = {Zhuang, W. X. and Wang, J. R. and Lin, H. T. and Shih, C. and Huang, K. C. and Dept. of Engineering and System Science, National Tsing-Hua Univ., Taiwan, No. 101, Kuang-Fu Road, Hsinchu 30013, Taiwan},
abstractNote = {The test facility IIST (INER Integral System Test) is a Reduced-Height and Reduced-Pressure (RHRP) integral test loop, which was constructed for the purposes of conducting thermal hydraulic and safety analysis of the Westinghouse three-loop PWR Nuclear Power Plants. The main purpose of this study is to develop and verify TRACE models of IIST through the IIST small break loss of coolant accident (SBLOCA) experiments. First, two different IIST TRACE models which include a pipe-vessel model and a 3-D vessel component model have been built. The steady state and transient calculation results show that both TRACE models have the ability to simulate the related IIST experiments. Comparing with IIST SBLOCA experiment data, the 3-D vessel component model has shown better simulation capabilities so that it has been chosen for all further thermal hydraulic studies. The second step is the sensitivity studies of two phase multiplier and subcooled liquid multiplier in choked flow model; and two correlation constants in CCFL model respectively. As a result, an appropriate set of multipliers and constants can be determined. In summary, a verified IIST TRACE model with 3D vessel component, and fine-tuned choked flow model and CCFL model is established for further studies on IIST experiments in the future. (authors)},
doi = {},
url = {https://www.osti.gov/biblio/22107789}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Jul 01 00:00:00 EDT 2012},
month = {Sun Jul 01 00:00:00 EDT 2012}
}

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