Benchmark exercise on SBLOCA experiment of PWR PACTEL facility

Kouhia, Virpi; Riikonen, Vesa; Kauppinen, Otso-Pekka; Purhonen, Heikki; Austregesilo, H.; Banati, Jozsef; Cherubini, M.; D'Auria, Francesco Saverio; Inkinen, Pasi; Karppinen, Ismo; Král, Pavel; Peltokorpi, Lauri; Peltonen, Joanna; Weber, Sebastian

doi:10.1016/j.anucene.2013.04.004

Cited by 11 publications

(3 citation statements)

References 2 publications

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“…The APROS nodalization of PWR PACTEL was re-developed and modified from a former APROS nodalization of the original PACTEL facility (Leppänen, 2000;. Also, the experience gained from a PWR PACTEL benchmark exercise (Kouhia et al, 2013) has been utilized in the development of the APROS and TRACE nodalizations. Fig.…”

Section: Nodalizations Of Pwr Pactelmentioning

confidence: 99%

“…The PWR PACTEL test facility (Kouhia et al, 2013(Kouhia et al, , 2014 in LUT was constructed in 2009, and it is designed to be used in safety studies related to the thermal-hydraulics of PWRs with vertical inverted U-tube steam generators (SGs). The facility is partly based on the original PACTEL facility (Tuunanen et al, 1998; , 2006).…”

Section: Pwr Pactel Test Facilitymentioning

confidence: 99%

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Computer analyses on loop seal clearing experiment at PWR PACTEL

Kauppinen

Kouhia

Riikonen

et al. 2015

Annals of Nuclear Energy

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Section: Nodalizations Of Pwr Pactelmentioning

confidence: 99%

Section: Pwr Pactel Test Facilitymentioning

confidence: 99%

Computer analyses on loop seal clearing experiment at PWR PACTEL

Kauppinen

Kouhia

Riikonen

et al. 2015

Annals of Nuclear Energy

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“…In both simulation models, the 51 U-tubes of the PWR PACTEL steam generators were modelled with five parallel U-tube groups (lumped). The number of U-tube groups used in the steam generator model could have an influence on the calculation results and is discussed shortly in the SBLOCA benchmark exercise of PWR PACTEL (Kouhia et al, 2013). The benchmark exercise showed that using lower number of U-tube groups instead of the five parallel U-tube groups in the steam generator model the possible flow stagnation or reversal that took place during the transient cannot be captured in some of the U-tubes.…”

Section: Fig 12mentioning

confidence: 99%

System code analysis of accumulator nitrogen discharge during LOCA experiment at PWR PACTEL test facility

Kauppinen

Kouhia

Riikonen

et al. 2019

Nuclear Engineering and Design

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The hydroaccumulators in pressurized water reactors can inject nitrogen into the reactor system. In the primary system, nitrogen affects core cooling and accident management, both adversely and beneficially. The PWR PACTEL experiment NCG-13 have shown that during a hot leg SB LOCA, nitrogen in the primary side can block the primary to secondary heat transfer and thereby prevent the primary depressurization to the point needed for the long-term accident management. This paper presents the APROS and TRACE calculations of the PWR PACTEL NCG-13 experiment. Both codes calculate the transient progression and the timing of the main events satisfactorily, once the suitable options are selected and adjustments made. There is, however, one big discrepancy between the code simulations and the experiment: in the simulations, much more nitrogen is needed to get qualitatively the same behaviour. The difference is a factor of 2.5 by mass for stopping the depressurization and 4-6 to cause a core heat-up. This is of concern regarding the confidence in the codes, as the simulations underestimate the adverse effect of nitrogen on the core coolability. HIGHLIGHTS: Codes predict the transient behaviour and timing of the main events satisfactory  In the simulations, nitrogen stops the primary side depressurization  Amount of released nitrogen is larger in the simulations than in the experiment *Highlights (for review)

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Investigation on reverse flow phenomena in UTSGs under two-phase natural circulation with low steam quality

Chen

Hao

et al. 2018

Annals of Nuclear Energy

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Benchmark exercise on SBLOCA experiment of PWR PACTEL facility

Cited by 11 publications

References 2 publications

Computer analyses on loop seal clearing experiment at PWR PACTEL

Computer analyses on loop seal clearing experiment at PWR PACTEL

System code analysis of accumulator nitrogen discharge during LOCA experiment at PWR PACTEL test facility

Investigation on reverse flow phenomena in UTSGs under two-phase natural circulation with low steam quality

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