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Modification of TTL-1 Thermo hydraulic Test Loop for Study of SB-LOCA in Low Pressure and Temperature Conditions

Taherzadeh Fard, Morteza | 2009

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  1. Type of Document: M.Sc. Thesis
  2. Language: Farsi
  3. Document No: 39703 (46)
  4. University: Sharif University of Technology
  5. Department: Energy Engineering
  6. Advisor(s): Vosoughi, Naser; Jafari, Jalil
  7. Abstract:
  8. In this thesis, TTL-1 thermo hydraulic test loop which was constructed in the Nuclear Science and Technology Research Institute (NSTRI) has been modified. These modifications include changing core section from one fuel rod to a fuel assembly with triangular arrangement, adding a pressurizer on the hot leg of loop, an accumulator, LOCA valve and installation of new sensors for upgrading of data acquisition system and modification of loop piping design. By these modifications, we will able to study different accidents such as LOHA, LOFA and LOCA and validate nuclear thermo hydraulic codes. Moreover, this new thermo hydraulic test loop (TTL-2) has been modeled by RELAP5/MOD3.2 in order to verify this code for low pressure and velocity conditions. This code has been prepared for the U. S. Nuclear Regulatory Commission by IDAHO laboratory for modeling of nuclear power reactor but its new version has been modified to be able model research reactors (low pressure and velocity conditions). Experimental data from TTL-2 and obtained results from RELAP5 code have been compared. A reasonable agreement between the results show that the RELAP5/MOD3.2 γ has capability to model DBA accidents at LP LV conditions such as nuclear research reactors.

  9. Keywords:
  10. Experimental Results ; RELAP5 Code ; Thermohydraulic Test Loop-2 ; Cooling System Accident Loss

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