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Transient Test of a NSSS Thermal-Hydraulic Module for the Nuclear Power Plant Simulator Using a Best-Estimate Code, RETRAN

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Systems Modeling and Simulation: Theory and Applications (AsiaSim 2004)

Part of the book series: Lecture Notes in Computer Science ((LNAI,volume 3398))

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Abstract

Korea Electric Power Research Institute (KEPRI) developed real-time simulation Thermal hydraulic model (ARTS) which is based on the best-estimate code, RETRAN. It was adapted Kori unit 1 nuclear power plant analyzer (NPA). This paper describes the result of the some of steady and transient tests of the Kori unit 1 NPA. The simulated results are compared and reviewed with the plant data and calculated reference data.

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References

  1. Suh, J.S., et al.: The Development of Virtual Simulator for Kori #1 Power Plant. KEPRI (2002)

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  2. Lee, M.S., et al.: Upgrade of the KNPEC-2 Simulator, 01-KEPRI-251. KEPRI (2001)

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  3. Kim, K.D., et al.: Development of An NSSS Thermal-Hydraulic Program for the KNPEC-2 Simulator Using a Best-Estimate Code: Part I. Code Development. In: Proc. KNS Spring Meeting (2001)

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  4. Suh, J.S.: Development of a Nuclear Steam Supply System Thermal -Hydraulic Module for the Nuclear Power Plant Simulator Using a Best-Estimate Code, RETRAN, Ph.D. Thesis, Department of Nuclear Engineering, Hanyang University (2004)

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  5. Paulsen, M.P., et al.: RETRAN 3D code manual, EPRI NP-7450, Electric Power Research Institute (1998)

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  6. Nuclear Power Plant Simulators for Use in Operator Training and Examination, ANSI/ANS-3.5-1998, American Nuclear Society (1998)

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Author information

Authors and Affiliations

  1. Korea Electric Power Research Institute, 103-16 Yuseong-Gu, Daejeon, Korea

    Myeong-Soo Lee, In-Yong Seo, Yo-Han Kim & Yong-Kwan Lee

  2. Future and Challenge Tech., San 56-1, Sillim-dong, Gwanak-gu, Seoul, Korea

    Jae-Seung Suh

Authors
  1. Myeong-Soo Lee
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  2. In-Yong Seo
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  3. Yo-Han Kim
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  4. Yong-Kwan Lee
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  5. Jae-Seung Suh
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Editor information

Editors and Affiliations

  1. Department of Computer Science & Engineering, Korea University, 1, 5-ga, Anam-dong, SungBuk-gu, 136-701, Seoul, Korea

    Doo-Kwon Baik

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© 2005 Springer-Verlag Berlin Heidelberg

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Lee, MS., Seo, IY., Kim, YH., Lee, YK., Suh, JS. (2005). Transient Test of a NSSS Thermal-Hydraulic Module for the Nuclear Power Plant Simulator Using a Best-Estimate Code, RETRAN. In: Baik, DK. (eds) Systems Modeling and Simulation: Theory and Applications. AsiaSim 2004. Lecture Notes in Computer Science(), vol 3398. Springer, Berlin, Heidelberg. https://doi.org/10.1007/978-3-540-30585-9_59

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  • DOI: https://doi.org/10.1007/978-3-540-30585-9_59

  • Publisher Name: Springer, Berlin, Heidelberg

  • Print ISBN: 978-3-540-24477-6

  • Online ISBN: 978-3-540-30585-9

  • eBook Packages: Computer ScienceComputer Science (R0)

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