Natural circulation and stability performance of BWRs (NACUSP)


Natural circulation and stability performance of BWRs (NACUSP)

Aguirre, C.; Caruge, D.; Castrillo, F.; Dominicus, G.; Geutjes, A. J.; Saldo, V.; van der Hagen, T. H. J. J.; Hennig, D.; Huggenberger, M.; Ketelaar, K. C. J.; Manera, A.; Munoz-Cobo, J. L.; Prasser, H.-M.; Rohde, U.; Royer, E.; Yadigaroglu, G.

From the beginning of BWR technology it was realized that a BWR can become unstable under particular circumstances caused by a feedback between the thermal-hydraulics and the neutronics. This instability can result in oscillations of the power and the flow rate, which is an unwanted phenomenon.

The NACUSP project addresses the stability issues in current and future BWRs by expanding the basic understanding through well structured testing and analyses of experimental data, by analyses of existing operational stability data from three different European reactors (Forsmark, Leibstadt, Cofrentes), by applying this knowledge via efficient models and validated computer codes to operating reactors and reactor designs, and by developing general guidelines for reactor operation and design on how to avoid BWR instabilities.
In order to cover the parameter range as efficiently as possible, four existing, sophisticated thermohydraulic test facilities (CLOTAIRE, DESIRE, CIRCUS and PANDA) have been selected. To extrapolate from small-scale separate-effect testing conditions to full-scale integral reactor conditions one needs to rely on the performance of computer codes (MONA, ATHLET , RAMONA-3(-5), LAPUR-V, DWOS, FLICA, SAPHYR, RELAP5/MOD3,TRAC-BF1). For specific items CFD codes are applied as well. Within NACUSP a linear stability analysis tool is developed.
Four of the three experimental facilities within the project have yielded a large, unique database.
Natural-circulation and stability characteristics at nominal pressure were collected from extensive experiments at the DESIRE facility. Low-pressure characteristics were measured at the PANDA (large scale) and the CIRCUS (small scale) facility.
The phenomena encountered (flow rate and stability trends, the occurrence of flashing induced oscillations) can be explained from basic physical models and are now well understood.
Several thermal-hydraulic codes have been benchmarked—some successfully, others with limited success—against these data.
The CLOTAIRE (nominal pressure, large scale) facility has been modified and is now ready for experiments.
Nuclear power plant data from three BWRs (Cofrentes, Forsmark and Leibstadt) have been collected. A very complete set of reactor data was obtained from measurements at the Leibstadt BWR during cycle-19. During this test, which was performed within the NACUSP project, safe reactor operation was demonstrated at extreme conditions, covering the entire power-flow map.
State-of-the-art, coupled thermal-hydraulic—neutronics codes are being benchmarked on these data.
The development of an easy to use, rapid and efficient analytical tool for parametric studies on BWR stability is in progress.
The last year of NACUSP will be devoted to finalising the before mentioned activities and to use the tools developed and the experience obtained for developing general guidelines for designing and operating BWRs.

Keywords: natural circulation; BWR; instability

  • Nuclear Engineering and Design (2005)235, 401-409

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