Home Technology 3RIP trip startup test simulation of TRACE/PARCS model for Lungmen ABWR under different power and flow conditions
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3RIP trip startup test simulation of TRACE/PARCS model for Lungmen ABWR under different power and flow conditions

  • Shu-Ming Yang , Hao-Tzu Lin , Jong-Rong Wang , Hsiung-Chih Chen , Chunkuan Shih and Shao-Wen Chen
Published/Copyright: December 12, 2015
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Kerntechnik
From the journal Kerntechnik Volume 80 Issue 6

Abstract

Lungmen nuclear power plant project started long time ago, it is not yet commercially operated but Taiwan Power Company has already prepared for its startup tests. 3RIP trip startup test is one of them. Three of the 10 RIPs will be manually tripped in the test. Response of the plant for this transient will be watched and recorded to check if the test criteria are satisfied. This paper is a result of code simulation of 3RIP trip startup test of Lungmen ABWR nuclear power plant. Thermal hydraulic code TRACE coupled with neutronics code PARCS were used to build the simulation model of Lungmen nuclear power plant. Startup tests under different plant power and flow conditions are considered in this research. A sensitivity study on the impact of different pump moment of inertia has been performed. Simulation results with TRACE and PARCS shows that the acceptance criteria for this startup test can be satisfied and the impact of different pump inertia is little.

Kurzfassung

Für das noch nicht in Betrieb gegangene Kernkraftwerk Lungmen wurden Vorbereitungen für die Anlaufprüfung getroffen. Die 3RIP-Anlaufprüfung ist eine davon. Drei der 10 internen Reaktorpumpen (RIP) werden bei dem Test manuell in Gang gesetzt. Die Rückmeldung des Systems für diese Transiente wird beobachtet und aufgezeichnet um die Erfüllung der Testkriterien zu überprüfen. Dieser Beitrag ist das Ergebnis der Simulation der 3RIP-Anlaufprüfung beim Kernkraftwerk Lungmen. Für die Simulation wurde der Thermohydraulik-Code TRACE, gekoppelt mit dem Neutronen-Code PARCS, verwendet. Eine Sensitvitätsstudie zum Einfluss der Trägheitsmomente der verschiedenen Pumpen wurde durchgeführt. Die Simulationsergebnisse mit Hilfe von TRACE und PARCS zeigen, dass die Akzeptanzkriterien für die Anlaufprüfung erfüllt werden können und der Einfluss der Trägheit der verschiedenen Pumpen gering ist.

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References

1 Taiwan Power Company: Lungmen nuclear power station startup test procedure – three RIPs trip test, STP-28B-HP, 2008Search in Google Scholar

2 Taiwan Power Company: Lungmen nuclear power station startup test procedure – three RIPs trip test, STP-28B-MP, 2008Search in Google Scholar

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Received: 2015-07-20
Published Online: 2015-12-12
Published in Print: 2015-12-17

© 2015, Carl Hanser Verlag, München

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Considering the uncertainties in empirical correlations for vertical countercurrent flow limitation (CCFL) with TRACE
  7. 3RIP trip startup test simulation of TRACE/PARCS model for Lungmen ABWR under different power and flow conditions
  8. Development of a new analytic function expansion nodal code, HexDANM, for solving the neutron diffusion equation in hexagonal-Z geometry
  9. Laser cleaning of steam generator tubing based on acoustic emission technology
  10. Axial enrichment profile in advance nuclear energy power plant at supercritical-pressures
  11. Analysis of the small break loss of coolant accident in the VVER-1000/V446 reactor
  12. Thermal hydraulic analysis of reactivity accidents in MTR research reactors using RELAP5
  13. Depletion of Gadolinium burnable poison in a PWR assembly with high burnup fuel
  14. Nuclear model calculations on cyclotron production of 51Cr
  15. Radiotracer application for characterization of nuclear grade anion exchange resins Tulsion A-23 and Dowex SBR LC
  16. Solving the criticality problem with the reflected boundary condition for the triplet anisotropic scattering with the modified FN method
https://doi.org/10.3139/124.110557

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Considering the uncertainties in empirical correlations for vertical countercurrent flow limitation (CCFL) with TRACE
  7. 3RIP trip startup test simulation of TRACE/PARCS model for Lungmen ABWR under different power and flow conditions
  8. Development of a new analytic function expansion nodal code, HexDANM, for solving the neutron diffusion equation in hexagonal-Z geometry
  9. Laser cleaning of steam generator tubing based on acoustic emission technology
  10. Axial enrichment profile in advance nuclear energy power plant at supercritical-pressures
  11. Analysis of the small break loss of coolant accident in the VVER-1000/V446 reactor
  12. Thermal hydraulic analysis of reactivity accidents in MTR research reactors using RELAP5
  13. Depletion of Gadolinium burnable poison in a PWR assembly with high burnup fuel
  14. Nuclear model calculations on cyclotron production of 51Cr
  15. Radiotracer application for characterization of nuclear grade anion exchange resins Tulsion A-23 and Dowex SBR LC
  16. Solving the criticality problem with the reflected boundary condition for the triplet anisotropic scattering with the modified FN method
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