In-vessel melt pool coolibility test—Description and results of LIVE experiments

Gaus-Liu, X.; Miassoedov, A.; Cron, T.; Wenz, Thomas

doi:10.1016/j.nucengdes.2010.09.001

Cited by 48 publications

(10 citation statements)

References 3 publications

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“…Significant investigations of corium and debris coolability in the vessel lower head were performed in the LIVE program at KIT (Gaus-Liu et al, 2010). A very large test matrix has been realised in the LIVE-3D facility, including variation in melt superheat, pouring conditions, external insulation.…”

Section: Coolability Of Corium In the Vessel Lower Headmentioning

confidence: 99%

Recent severe accident research synthesis of the major outcomes from the SARNET network

Dorsselaere

Auvinen

Beraha

et al. 2015

Nuclear Engineering and Design

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The SARNET network (Severe Accident Research NETwork of excellence), co-funded by the European Commission from 2004 to 2013, has allowed to significantly improve the knowledge on severe accidents and to disseminate it through courses and ERMSAR conferences. The major investigated topics, involving more than 250 researchers from 22 countries, were in- and ex-vessel corium/debris coolability, molten-core–concrete-interaction, steam explosion, hydrogen combustion and mitigation in containment, impact of oxidising conditions on source term, and iodine chemistry. The ranking of the high priority issues was updated to account for the results of recent international research and for the impact of Fukushima nuclear accidents in Japan. In addition, the ASTEC integral code was further developed to capitalize the new knowledge. The network has reached self-sustainability by integration in mid-2013 into the NUGENIA Association. The main activities and outcomes of the network are presented

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Section: Coolability Of Corium In the Vessel Lower Headmentioning

confidence: 99%

Recent severe accident research synthesis of the major outcomes from the SARNET network

Dorsselaere

Auvinen

Beraha

et al. 2015

Nuclear Engineering and Design

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“…This interface temperature has been experimentally validated by the following experimental programs: PHYTHER [27], SIMECO (RIT/KTH), RASPLAV [28] and more recently LIVE (KIT) [29].…”

Section: The Crust-melt Interface Temperature For a Homogeneous Meltmentioning

confidence: 99%

“…Work carried out as part of the OECD MASCA program [29] has shown that the complex physical phenomena occurring could reduce the "available" mass of metal. These phenomena include:…”

Section: Limitation Associated With the Minimum Mass Of Molten Steel mentioning

confidence: 99%

In-Vessel Core Degradation

2012

Nuclear Safety in Light Water Reactors

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“…Accordingly, the RPV failure is determined as time-and temperature-dependent process. In disclosing the complexity of the structural behaviors, several experimental programs such as FOREVER, USNRC/SNL, CORVIS, and LIVE had been performed (Willschutz et al, 2001(Willschutz et al, , 2006Nicolas et al, 2003;Adroguer et al, 2003;Gaus-Liu et al, 2010;Buck et al, 2010), the results of which validated the predictability on the failure time, mode and site by using the finite element method (FEM). The already conducted experiment span a wide range of pressure (0.2-10 MPa) and temperature gradient (130-1500 • C) (Theofanous et al, 1997).…”

Section: Introductionmentioning

confidence: 99%

Structural integrity investigation for RPV with various cooling water levels under pressurized melting pool

et al. 2018

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Abstract. The strategy denoted as "in-vessel retention (IVR)" is widely used in severe accident (SA) management by most advanced nuclear power plants. The essence of IVR mitigation is to provide long-term external water cooling in maintaining the reactor pressure vessel (RPV) integrity. Actually, the traditional IVR concept assumed that RPV was fully submerged into the water flooding, and the melting pool was depressurized during the SA. The above assumptions weren't seriously challenged until the occurrence of Fukushima accident on 2011, suggesting the structural behavior had not been appropriately assessed. Therefore, the paper tries to address the structure-related issue on determining whether RPV safety can be maintained or not with the effect of various water levels and internal pressures created from core meltdown accident. In achieving it, the RPV structural behaviors are numerically investigated in terms of several field parameters, such as temperature, deformation, stress, plastic strain, creep strain, and total damage. Due to the presence of high temperature melt on the inside and water cooling on the outside, the RPV failure is governed by the failure mechanisms of creep, thermal-plasticity and plasticity. The creep and plastic damages are interacted with each other, which further accelerate the failure process. Through detailed investigation, it is found that the internal pressure as well as water levels plays an important role in determining the RPV failure time, mode and site.

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In-vessel melt pool coolibility test—Description and results of LIVE experiments

Cited by 48 publications

References 3 publications

Recent severe accident research synthesis of the major outcomes from the SARNET network

Recent severe accident research synthesis of the major outcomes from the SARNET network

In-Vessel Core Degradation

Structural integrity investigation for RPV with various cooling water levels under pressurized melting pool

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