Assessment of reactor vessel integrity (ARVI)

Sehgal, B.R.; Karbojian, Aram; Giri, Asis; Kymäläinen, Olli; Bonnet, Jean-Michel; Ikkonen, K.; Sairanen, Risto; Bhandari, S.; Buerger, Μ. J.; Dienstbier, J.; Téchy, Zsolt; Theofanous, T.G.

doi:10.1016/j.nucengdes.2004.08.055

Cited by 29 publications

(12 citation statements)

References 3 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…On the contrary to our results, studies, available in the literature, have shown an increasing side wall heat flux with decreasing metal layer height (Theofanous et al, 1996;Rempe et al, 1997;Sehgal et al, 1999Sehgal et al, , 2000Sehgal et al, , 2005.…”

Section: Parameter Studies On the Thickness Of The Metal Layercontrasting

confidence: 99%

“…A comparison of the different results in (Sehgal et al, 1999(Sehgal et al, , 2005 and the analysis performed in this study shows, that the amount of heat, which is released from the melt surface by radiation appears to be the key phenomenon. In (Sehgal et al, 1999) the initial melt pool temperature (2000 K) was considerably lower than in this study, which results in a lower fraction of heat released through radiation.…”

Section: Parameter Studies On the Thickness Of The Metal Layermentioning

confidence: 70%

“…Experimental programmes, investigating the behaviour of a molten pool, heat fluxes from the pool, are performed by (Kymäläinen et al, 1993(Kymäläinen et al, , 1994Helle et al, 1997;Helle and Kymäläinen, 1998;Bonnet, 1998;Theofanous et al, 1997b;Asmolov et al, 2001Asmolov et al, , 2003aAsmolov et al, , 2003bAsmolov and Tsurikov, 2004;Bechta et al, 2001Bechta et al, , 2008aBechta et al, , 2008bSehgal et al, 2005;Buck et al, 2008;Miassoedov et al, 2008;Kretzschmar and Fluhrer, 2008;Gaus-Liu et al, 2010;Park et al, 2013).…”

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Investigations on in-vessel melt retention by external cooling for a generic VVER-1000 reactor

Tusheva

Altstadt

Willschütz

et al. 2015

Annals of Nuclear Energy

View full text Add to dashboard Cite

Section: Parameter Studies On the Thickness Of The Metal Layercontrasting

confidence: 99%

Section: Parameter Studies On the Thickness Of The Metal Layermentioning

confidence: 70%

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Investigations on in-vessel melt retention by external cooling for a generic VVER-1000 reactor

Tusheva

Altstadt

Willschütz

et al. 2015

Annals of Nuclear Energy

View full text Add to dashboard Cite

“…It was concluded that an increased sulphur (S) content could be the reason for a rather brittle failure (low creep fracture strain 3 cr frac ), whereas low S provides a rather ductile failure with large necking and high creep fracture strains [59]. This effect could also be observed in the FOREVER test series [60] [61].…”

Section: Mechanical Behavior Of the Vesselmentioning

confidence: 99%

In-Vessel Core Degradation

2012

Nuclear Safety in Light Water Reactors

View full text Add to dashboard Cite

“…In order to investigate integrity of lower head, several improvements have been done to current system codes to simulate thermal hydraulic behavior of molten materials in lower head, including MELCOR (Gauntt, 2005), SCDAP/RELAP5 (The SCDAP/RELAP5-3D Code Development Team, 2003), MAAP (MAAP code development Team, 1994), ATHLET-CD (Austregesilo, 2012). Alternatively, some codes are specially developed to evaluate integrity of the reactor pressure vessel (RPV) wall cooled from outside, such as VESSEL, MVITA (Sehgal et al, 2003), ERI-IVRAM (Esmaili and Khatib-Rahbar, 2004) and VESTA (Rempe et al, 1997). Since the temperature field of lower head is decisive factor in identifying the effectiveness of IVR This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).…”

Section: Introductionmentioning

confidence: 99%

A two dimensional approach for temperature distribution in reactor lower head during severe accident

Cao

Liu

2015

Annals of Nuclear Energy

View full text Add to dashboard Cite

a b s t r a c tIn order to evaluate the safety margin during a postulated severe accident, a module named ASAP-2D (Accident Simulation on Pressure vessel-2 Dimensional), which can be implemented into the severe accident simulation codes (such as ATHLET-CD), is developed in Shanghai Jiao Tong University. Based on two-dimensional spherical coordinates, heat conduction equation for transient state is solved implicitly. Together with solid vessel thickness, heat flux distribution and heat transfer coefficient at outer vessel surface are obtained. Heat transfer regime when critical heat flux has been exceeded (POST-CHF regime) could be simulated in the code, and the transition behavior of boiling crisis (from spatial and temporal points of view) can be predicted.The module is verified against a one-dimensional analytical solution with uniform heat flux distribution, and afterwards this module is applied to the benchmark illustrated in NUREG/CR-6849. Benchmark calculation indicates that maximum heat flux at outer surface of RPV could be around 20% lower than that of at inner surface due to two-dimensional heat conduction. Then a preliminary analysis is performed on the integrity of the reactor vessel for which the geometric parameters and boundary conditions are derived from a large scale advanced pressurized water reactor. Results indicate that heat flux remains lower than critical heat flux. Sensitivity analysis indicates that outer heat flux distribution is more sensitive to input heat flux distribution and the transition boiling correlation than mass flow rate in external reactor vessel cooling (ERVC) channel, and the correlation for molten vessel and ERVC coolant inlet temperature.According to the results achieved, the new developed module shows good applicability to simulate the pressure vessel behavior during melt pool formation. Thus it can be applied for the future study of the severe accidents relating to lower head integrity.

show abstract

Assessment of reactor vessel integrity (ARVI)

Cited by 29 publications

References 3 publications

Investigations on in-vessel melt retention by external cooling for a generic VVER-1000 reactor

Investigations on in-vessel melt retention by external cooling for a generic VVER-1000 reactor

In-Vessel Core Degradation

A two dimensional approach for temperature distribution in reactor lower head during severe accident

Contact Info

Product

Resources

About