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Published May 2008 | Version v1
Miscellaneous

Analysis of Condensation in a Vertical Tube in the presence of Noncondensable Gases using MARS code

  • 1. Seoul National Univ., (Korea, Republic of)

Description

Although many thermal-hydraulic experiments have been performed in Korea, their experimental data are not systematically managed and effectively used for nuclear power plant design or research, for example, validating MARS code. So, in order to collect experimental data and assess the reliabilities of them, the project named 'Assessment of Thermal-hydraulic Experiment Database and Improvement of MARS Code' is underway. Last year, 2007, explorations on what experiments were performed and where they were performed in have been completed and procedures used to evaluate the reliability and usefulness of experiments were developed. In this year, second year, thermalhydraulic database system will be established and simulation using MARS code will be performed. Next year, detailed comparisons experimental data with MARS code calculation results will be conducted and, as an ultimate goal, suggestions on improvement of MARS code will be discussed. As a part of the project, the condensation experiments performed in POSTECH were investigated. Raw data, papers and reports were collected and analyzed. To assess MARS capacity on condensation, experimental data were compared with MARS code predictions. In this paper, experiment and MARS modeling are briefly described and comparison results are presented

Part of:
Proceedings of the Korean Nuclear Society Spring Meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS spring meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2008 spring meeting of the KNS
Dates
29-30 May 2008
Place
Kyeongju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
39109268
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Numerical Data, Non-conventional Literature
Descriptors DEI
COMPUTERIZED SIMULATION; DESIGN; EXPERIMENTAL DATA; M CODES; NUCLEAR POWER PLANTS; THERMAL HYDRAULICS; TUBES
Descriptors DEC
COMPUTER CODES; DATA; FLUID MECHANICS; HYDRAULICS; INFORMATION; MECHANICS; NUCLEAR FACILITIES; NUMERICAL DATA; POWER PLANTS; SIMULATION; THERMAL POWER PLANTS

Optional Information

Notes
3 refs, 6 figs