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Development of a qualified nodalization for small-break LOCA transient analysis in PSB-VVER integral test facility by RELAP5 system code

Shahedi, S ; Sharif University of Technology | 2010

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  1. Type of Document: Article
  2. DOI: 10.1016/j.nucengdes.2010.06.024
  3. Publisher: 2010
  4. Abstract:
  5. This paper deals with development and qualification of a nodalization for modeling of the PSB-VVER integral test facility (ITF) by RELAP5/MOD3.2 code and prediction of its primary and secondary systems behaviors at steady state and transient conditions. The PSB-VVER is a full-height, 1/300 volume and power scale representation of a VVER-1000 NPP. A RELAP5 nodalization has been developed for PSB-VVER modeling and a nodalization qualification process has been applied for the developed nodalization at steady state and transient levels and a qualified nodalization has been proposed for modeling of the PSB ITF. The 11% small-break loss-of-coolant-accident (SBLOCA), i.e. rupture of one of the hydroaccumulators (HA) injection lines in the upper plenum (UP) region of reactor pressure vessel (RPV) below the hot legs (HL), inlets has been considered for nodalization qualification process. The influence of the different steam generator (SG) nodalizations on the RELAP5 results and on the nodalization qualification process has been examined. The "steady state" qualification level includes checking the correctness of the initial and boundary conditions and geometrical fidelity. In the "transient" qualification level, the time dependent results of the code calculation are compared with the experimental time trends from both the qualitative and quantitative point of view. For quantitative assessment of the results, a Fast Fourier Transform Based Method (FFTBM) has been used. The FFTBM was used to establish a range in which the steam generators nodalizations can vary
  6. Keywords:
  7. Code calculations ; Injection lines ; Integral test ; Qualification process ; Quantitative assessments ; Reactor Pressure Vessel ; Secondary system ; Steady state ; System codes ; Time dependent ; Time trends ; Transient conditions ; VVER-1000 ; Fast Fourier transforms ; Pressure vessels ; Steam generators ; Test facilities ; Transient analysis ; Mathematical models
  8. Source: Nuclear Engineering and Design ; Volume 240, Issue 10 , October , 2010 , Pages 3309-3320 ; 00295493 (ISSN)
  9. URL: http://www.sciencedirect.com/science/article/pii/S0029549310004437