Simulation of Loop Connection of RCPs during Commissioning Test of BNPP Using RELAP 5 Code to Two or Three Operating Ones

Zeynalian, MirHadi | 2019

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  1. Type of Document: M.Sc. Thesis
  2. Language: Farsi
  3. Document No: 51971 (46)
  4. University: Sharif University of Technology
  5. Department: Energy Engineering
  6. Advisor(s): Ghofrani, Mohammad Bagher
  7. Abstract:
  8. In order to ensure the safety of the plants, a set of commissioning tests based on international standards for nuclear power plants is carried out before operation. In this research, one of the Bushehr power plant commissioning tests, the loop connection primary circuit cooling pump test, was simulated using the RELAP5 code. In this test, the effects of loop connection primary circuit pumps on the thermohydraulic parameters and the eneterance of test-related systems was evaluated. After simulating the systems related to the test and extracting the results of the stable state, were evaluated the transient results was obtained with the experimental results of the test of loop connection the primary circuit of the primary circuit of Bushehr power plant was extracted by Tavana.This test is about the effect of entering the initial circuit cooling pumps when two or three other pumps are in operation. On the line, the coolant pump of the initial circuit of the reactor leads to a rapid increase in the flow rate of the cooling fluid in the core and an increase in the difference in pressure in the core, followed by a decrease in the average temperature of the core, which triggers thermal feedback, positive reactivity injection and increase Power level.In this research, to validate the simulation was carried out in a stable state, the thermohydraulic parameters of power, primary and secondary circuit pressure, the temperature of the base of coldleg and hotleg in the pumps on and off, and the height of the water inside the pressurized and the steam generator was studied and was analyzed by the results of the stable state The correct simulation code was shown, after which the first circuit cooling pump was illuminated in two separate stages and behind it, and the results of the code was evaluated with the experimental results of the test, and good agreement was observed between the results. The main factors in the discrepancy between the results were the lack of discrete data of the diagrams, the neutron information during the test, and the exact information on the flow of feedwater and safety valves
  9. Keywords:
  10. Bushehr Nuclear Power Plant ; Loop Connection Test ; RELAP5 Code ; Thermohydraulic Analysis ; Experimental Results

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