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Lee, Deokjung
Computational Reactor physics & Experiment lab (CORE Lab)
Research Interests
  • Reactor Analysis computer codes development
  • Methodology development of reactor physics
  • Nuclear reactor design(SM-SFR,PWR and MSR)

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Analysis of the OECD/NRC BWR turbine trip transient benchmark with the coupled thermal-hydraulics and neutronics code TRAC-M/PARCS

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Title
Analysis of the OECD/NRC BWR turbine trip transient benchmark with the coupled thermal-hydraulics and neutronics code TRAC-M/PARCS
Author
Lee, DeokjungDownar, TJUlses, AAkdeniz, BIvanov, KN
Issue Date
2004-10
Publisher
AMER NUCLEAR SOCIETY
Citation
NUCLEAR SCIENCE AND ENGINEERING, v.148, no.2, pp.291 - 305
Abstract
An analysis of the Peach Bottom Unit 2 Turbine Trip 2 (TT2) experiment has been performed using the U.S. Nuclear Regulatory Commission coupled thermal-hydraulics and neutronics code TRAC-M/ PARCS. The objective of the analysis was to assess the performance of TRAC-M/PARCS on a BWR transient with significance in two-phase flow and spatial variations of the neutron flux. TRAC-M/PARCS results are found to be in good agreement with measured plant data for both steady-state and transient phases of the benchmark. Additional analyses of four fictitious extreme scenarios are performed to provide a basis for code-to-code comparisons and comprehensive testing of the thermal-hydraulics/ neutronics coupling. The obtained results of sensitivity studies on the effect of direct moderator heating on transient simulation indicate the importance of this modeling aspect.
URI
https://scholarworks.unist.ac.kr/handle/201301/7406
URL
http://www.scopus.com/inward/record.url?partnerID=HzOxMe3b&scp=9144254622
ISSN
0029-5639
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