Steam generator tube rupture (SGTR) scenarios

Auvinen, Ari; Jokiniemi, Jorma; Lähde, Anna; Routamo, T.; Lundström, Petra; Tuomisto, H.; Dienstbier, J.; Güntay, S.; Suckow, D.; Dehbi, A.; Slootman, M.L.F.; Herranz, L.E.; Peyrés, V.; Polo, Jesús

doi:10.1016/j.nucengdes.2004.08.060

Cited by 49 publications

(18 citation statements)

References 4 publications

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“…A spontaneous SGTR could be an initiating event of the severe accident; or a severe accident could induce a SGTR by subjecting the tubes to large thermal and pressure loads; or other events like a sudden break in the steam line leading to a rapid depressurization of the secondary system could also induce simultaneous tube ruptures which could give rise to the reactor core melt (USNRC, 1990;Auvinen et al, 2005;Liao and Guentay, 2009;Macdonald et al, 1996). Regarding the bypass sequence, it could result from the SGTR (spontaneous or induced) as it increases the secondary side pressure which is likely to cause relief valves to lift on the secondary side.…”

Section: The Sgtr Severe Accident Scenariomentioning

confidence: 99%

“…As an example, Table 1.2.1 collects the maximum values of the conditions of a potential fault SG during the fission product release period of one of the most dominant SGTR accident scenarios of the Swiss Beznau NPP (based on PRA analysis; Auvinen et al, 2005). Depending on the SG region, the main processes governing aerosol removal when the secondary side is empty of water are the following (Güntay et al, 2000;Allelein et al, 2009).…”

Section: The Sgtr Severe Accident Scenariomentioning

confidence: 99%

“…Its first objective was to generate a comprehensive database on fission product retention in a steam generator. The second one was to verify and develop predictive models to support accident management interventions during steam generator tube rupture sequences (Auvinen et al, 2005). Its natural extension was the ARTIST project (AeRosol Trapping In a Steam Generator, 2003, a seven-phase project that sought to fulfill the database and model development (Güntay et al, 2004).…”

Section: Background and Frame Of The Workmentioning

confidence: 99%

“…These projects have demonstrated experimentally that some retention should be expected and that it would be highly dependent upon governing thermal-hydraulic conditions and the location and size of the break (Auvinen et al, 2005;Güntay et al, 2004;Herranz et al, 2006). Particularly, the presence of water in the secondary side appears to be a key factor (Güntay et al, 2004), since a substantial fraction of particles carried by gas might be scrubbed by the water.…”

Section: Background and Frame Of The Workmentioning

confidence: 99%

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A Theoretical Investigation of Aerosol Retention Within the Secondary Side of a Steam Generator Under a SGTR Severe Accident Sequence in a PWR Nuclear Power Plant

Prá¹

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Section: The Sgtr Severe Accident Scenariomentioning

confidence: 99%

Section: The Sgtr Severe Accident Scenariomentioning

confidence: 99%

Section: Background and Frame Of The Workmentioning

confidence: 99%

Section: Background and Frame Of The Workmentioning

confidence: 99%

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A Theoretical Investigation of Aerosol Retention Within the Secondary Side of a Steam Generator Under a SGTR Severe Accident Sequence in a PWR Nuclear Power Plant

Prá¹

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“…The EU-SGTR project of the 5 th Framework Program of EURATOM (Auvinen et al 2005) was the only program aimed to investigate source term retention during SGTR sequences. CIEMAT results of the project were analyzed and deeply discussed as starting point of this thesis from were several specifics were obtained .…”

Section: State Of Art On Aerosol Retention In the Secondary Side Of Amentioning

confidence: 99%

Experimental characterization of aerosol retention in the break stage of a dry steam generator in SGTR sequences.

Velasco¹,

Javier²

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Severe accident Steam Generator Tube Rupture (SGTR) sequences are identified as major contributors to risk of Pressurized Water Reactors (PWR). Their relevance lies in the potential radioactive release, in form of aerosol, from reactor coolant system to the environment. However, radioactive particles could be partially retained in the secondary side of the steam generator, even in the absence of water. Lack of knowledge on the source term attenuation capability of the steam generator has avoided its consideration in probabilistic safety studies and severe accident management guidelines. As a consequence, the steam generator filtering capability is not usually taken into account either in the probabilistic risk assessment of nuclear safety or in the severe accident management guidelines.This thesis describes the main activities and results of a bench-scale experimental program focused on getting insights into the aerosol retention in the break stage of the secondary side of a dry steam generator. The thesis is framed in the CIEMAT contribution to the ARTIST project (2003)(2004)(2005)(2006)(2007)(2008) which was supported by te Spanish Nuclear Regulatory Commission (CSN). The general objective of the work was to generate a comprehensive database on fission product retention in the break stage of a dry steam generator during a severe accident SGTR sequence. The specific objectives were to assess the influence of aerodynamic flow field as well as the influence of particle nature on aerosol deposition in the tube bundle. To do so, a scaled-down mock-up with representative dimensions of a real SG was built. The aerodynamic characterization of the flow field within the break stage of the bundle was done via 2D PIV (particle image velocimetry) technique. The particle nature influence on retention was characterized through aerosol retention experiments in the tube bundle mock-up. The major variables investigated were the type of breach (guillotine vs fish-mouth), the inlet gas mass flow rate (75-250 kg/h) and the particle type (polidispersed TiO 2 agglomerates vs. solid, monodisperse SiO 2 spheres).The aerodynamic campaign permitted to characterize the flow field close to the breach for both type of breaches and to asses their similarities. Results showed that the jet flows within the tube bundle following a generic quasi-parabolic trajectory evolving from an oblique cross flow configuration to an axial one. Mean flow field near the breach is substantially affected by the entrainment of initially stagnant gas into the jet. This effect is fostered by the presence of tubes and their tight packing. Jet penetration and turbulence intensity are considerably enhanced when increasing inlet gas mass flow rate.The results of the aerosol campaign showed that particle nature substantially affects retention in the tube bundle: mass retention was low for TiO 2 agglomerates (less than 30%) whereas it was much higher for SiO 2 particles (around 85%). Collection efficiency is also affected by gas mass flow rate: its sensitivity ...

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Numerical simulation of the effects of trefoil tube support plates on the flow and heat transfer characteristics of a steam generator

et al. 2020

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Steam generator tube rupture (SGTR) scenarios

Cited by 49 publications

References 4 publications

A Theoretical Investigation of Aerosol Retention Within the Secondary Side of a Steam Generator Under a SGTR Severe Accident Sequence in a PWR Nuclear Power Plant

A Theoretical Investigation of Aerosol Retention Within the Secondary Side of a Steam Generator Under a SGTR Severe Accident Sequence in a PWR Nuclear Power Plant

Experimental characterization of aerosol retention in the break stage of a dry steam generator in SGTR sequences.

Numerical simulation of the effects of trefoil tube support plates on the flow and heat transfer characteristics of a steam generator

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