Effects of Secondary Circuit Modeling on Results of Pressurized Water Reactor Main Steam Line Break Benchmark Calculations with New Coupled Code TRAB-3D/SMABRE
| Autor: | Antti Daavittila, Riitta Kyrki-Rajamäki, Anitta Hämäläinen |
|---|---|
| Rok vydání: | 2003 |
| Předmět: |
Nuclear and High Energy Physics
Neutron transport Maximum power principle Nuclear engineering Flow (psychology) Pressurized water reactor Nuclear reactor Condensed Matter Physics law.invention Power (physics) Thermal hydraulics Nuclear Energy and Engineering law Environmental science Transient (oscillation) |
| Zdroj: | Daavittila, A, Hämäläinen, A & Kyrki-Rajamäki, R 2003, ' Effects of secondary circuit modeling on results of pressurized water reactor main steam line break benchmark calculations with new coupled code TRAB-3D/SMABRE ', Nuclear Technology, vol. 142, no. 2, pp. 116-123 . < http://www.ans.org/pubs/journals/nt/a_3377 > |
| ISSN: | 1943-7471 0029-5450 |
| DOI: | 10.13182/nt03-a3377 |
| Popis: | All of the three exercises of the Organization for Economic Cooperation and Development/Nuclear Regulatory Commission pressurized water reactor main steam line break (PWR MSLB) benchmark were calculated at VTT, the Technical Research Centre of Finland. For the first exercise, the plant simulation with point-kinetic neutronics, the thermal-hydraulics code SMABRE was used. The second exercise was calculated with the three-dimensional reactor dynamics code TRAB-3D, and the third exercise with the combination TRAB-3D/SMABRE. VTT has over ten years' experience of coupling neutronic and thermal-hydraulic codes, but this benchmark was the first time these two codes, both developed at VTT, were coupled together. The coupled code system is fast and efficient; the total computation time of the 100-s transient in the third exercise was 16 min on a modern UNIX workstation. The results of all the exercises are similar to those of the other participants. In order to demonstrate the effect of secondary circuit modeling on the results, three different cases were calculated. In case 1 there is no phase separation in the steam lines and no flow reversal in the aspirator. In case 2 the flow reversal in the aspirator is allowed, but there is no phase separation in the steam lines. Finally, in case 3 the drift-flux model is used for the phase separation in the steam lines, but the aspirator flow reversal is not allowed. With these two modeling variations, it is possible to cover a remarkably broad range of results. The maximum power level reached after the reactor trip varies from 534 to 904 MW, the range of the time of the power maximum being close to 30 s. Compared to the total calculated transient time of 100 s, the effect of the secondary side modeling is extremely important. |
| Databáze: | OpenAIRE |
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