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Modeling of Boushehr NPP (as built) and Analysis of Large Break Loss of Coolant Accident (LB-LOCA) Using RELAP5/MOD3.2 System Code

Khalife Shoushtari, Mohammad Mahdi | 2010

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  1. Type of Document: M.Sc. Thesis
  2. Language: Farsi
  3. Document No: 41272 (46)
  4. University: Sharif University of Technology
  5. Department: Energy Engineering
  6. Advisor(s): Vossoughi, Naser; Jafari, Jalil
  7. Abstract:
  8. In this work the large break loss of coolant accident at Boushehr Nuclear Power Plant (NPP) has been studied. At first, primary and secondary side’s components which play important role in the accident have been modeled using RELAP5/MOD3.2 GAMMA system code. The components are: reactor pressure vessel, main pipe lines, main coolant pumps, pressurizer, steam generators, steam lines, emergency core cooling accumulators, boron solution supply tanks and pumps (LP& HP) and KWU accumulators. After preparing the input file and running the code, thermal hydraulic properties such as radial distribution of temperature in fuel rods, temperature distribution in steam generator primary and secondary sides, coolant channels, mass flows, pressure differences, pressurizer water level and so on has been extracted. The reactor core has been divided into four channels in this model. Three of them are channels with nuclear power generation and the other is core bypass. In the hot channel a hot rod, which is the most powered fuel rod in the core, has been considered to study the maximum fuel center and maximum clad surface temperatures, critical heat flux and maximum linear power. Primary and secondary sides of the steam generators have been divided into eight and four channel, respectively. After thermo-hydraulic modeling of Boushehr NPP in last work and reaching steady state condition, large break loss of coolant accident in reactor inlet has been considered. The accident conditions have been considered according to Boushehr NPP final safety analysis report. It is assumed that the accident occurs at worst conditions; the break is double ended, one of the accumulators which connected to the RPC doesn’t work and boron solution high and low pressure injection pumps only supply to loop 1 and 4. Assessment of the results has been made using Boushehr NPP Final Safety Analysis Report. In this work, also, operation of KWU accumulators has been considered. No violation from the acceptance criteria shows that the plant is safe and emergency systems are suitable under LB-LOCA conditions
  9. Keywords:
  10. Bushehr Nuclear Power Plant ; RELAP5 Code ; Thermohydraulic Model ; Large Break Less-of-Coolant Accident (LB-LOCA) ; Final Safety Analysis Report (FSAR) ; KWU Accumulator

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