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Title: Development of flow network analysis code for block type VHTR core by linear theory method

Abstract

VHTR (Very High Temperature Reactor) is high-efficiency nuclear reactor which is capable of generating hydrogen with high temperature of coolant. PMR (Prismatic Modular Reactor) type reactor consists of hexagonal prismatic fuel blocks and reflector blocks. The flow paths in the prismatic VHTR core consist of coolant holes, bypass gaps and cross gaps. Complicated flow paths are formed in the core since the coolant holes and bypass gap are connected by the cross gap. Distributed coolant was mixed in the core through the cross gap so that the flow characteristics could not be modeled as a simple parallel pipe system. It requires lot of effort and takes very long time to analyze the core flow with CFD analysis. Hence, it is important to develop the code for VHTR core flow which can predict the core flow distribution fast and accurate. In this study, steady state flow network analysis code is developed using flow network algorithm. Developed flow network analysis code was named as FLASH code and it was validated with the experimental data and CFD simulation results. (authors)

Authors:
;  [1];  [2];  [1]
  1. Dept. of Nuclear Engr., Seoul National Univ., Daehak-dong, Gwanak-gu, Seoul, 151-742 (Korea, Republic of)
  2. Dept. of Nuclear and Energy Engr, Dongguk Univ., Seokjang-Dong, Gyeongju, Gyeongsangbuk-Do, 780-714 (Korea, Republic of)
Publication Date:
Research Org.:
American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
OSTI Identifier:
22105955
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; 10 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:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; ALGORITHMS; COMPUTERIZED SIMULATION; COOLANTS; EXPERIMENTAL DATA; FLOW MODELS; FLUID MECHANICS; FUEL ELEMENTS; HEXAGONAL CONFIGURATION; HTGR TYPE REACTORS; NETWORK ANALYSIS; PIPES; REACTOR CORES; STEADY-STATE CONDITIONS; TEMPERATURE RANGE 0400-1000 K

Citation Formats

Lee, J. H., Yoon, S. J., Park, J. W., and Park, G. C. Development of flow network analysis code for block type VHTR core by linear theory method. United States: N. p., 2012. Web.
Lee, J. H., Yoon, S. J., Park, J. W., & Park, G. C. Development of flow network analysis code for block type VHTR core by linear theory method. United States.
Lee, J. H., Yoon, S. J., Park, J. W., and Park, G. C. 2012. "Development of flow network analysis code for block type VHTR core by linear theory method". United States.
@article{osti_22105955,
title = {Development of flow network analysis code for block type VHTR core by linear theory method},
author = {Lee, J. H. and Yoon, S. J. and Park, J. W. and Park, G. C.},
abstractNote = {VHTR (Very High Temperature Reactor) is high-efficiency nuclear reactor which is capable of generating hydrogen with high temperature of coolant. PMR (Prismatic Modular Reactor) type reactor consists of hexagonal prismatic fuel blocks and reflector blocks. The flow paths in the prismatic VHTR core consist of coolant holes, bypass gaps and cross gaps. Complicated flow paths are formed in the core since the coolant holes and bypass gap are connected by the cross gap. Distributed coolant was mixed in the core through the cross gap so that the flow characteristics could not be modeled as a simple parallel pipe system. It requires lot of effort and takes very long time to analyze the core flow with CFD analysis. Hence, it is important to develop the code for VHTR core flow which can predict the core flow distribution fast and accurate. In this study, steady state flow network analysis code is developed using flow network algorithm. Developed flow network analysis code was named as FLASH code and it was validated with the experimental data and CFD simulation results. (authors)},
doi = {},
url = {https://www.osti.gov/biblio/22105955}, journal = {},
number = ,
volume = ,
place = {United States},
year = {2012},
month = {7}
}

Conference:
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