Core loss during a severe accident (COLOSS)

Adroguer, B.; Bertrand, Frédèric; Chatelard, P.; Cocuaud, N.; Dorsselaere, J.P. Van; Bellenfant, L.; Knocke, D.; Bottomley, D.; Vrtílková, Věra; Bělovský, L.; Mueller, K.; Hering, W.; Homann, Ch.; Krauss, W.; Miassoedov, A.; Schanz, G.; Steinbrück, M.; Stuckert, J.; Hózer, Zoltán; Bandini, G.; Birchley, J.; Berlepsch, T.v.; Kleinhietpass, I.; Buck, M.; Benitez, J. A. Fernandez; Virtanen, E.; Marguet, Serge; Azarian, G.; Caillaux, A.; Plank, Helmut; Boldyrev, A.V.; Veshchunov, M.S.; Kobzar, V.; Zvonarev, Yu.A.; Goryachev, A. V.

doi:10.1016/j.nucengdes.2004.08.050

Cited by 32 publications

(8 citation statements)

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“…The driving force for the reaction is diffusion of oxygen from the UO 2 into the sheathing. This process has been extensively studied in single-effect laboratory crucible experiments, and models of the kinetics of the phenomenon have been proposed [168,[170][171][172][173][174][175][176][177][178][179][180][181][182][183][184][185][186].…”

Section: Moalem and Olandermentioning

confidence: 99%

“…The effects of fuel collapse, UO 2 /Zircaloy interaction and fuel dissolution have been studied with irradiated fuel samples in several high-temperature tests conducted out-reactor with PWR, Boiling Water Reactor (BWR) and MOX fuel samples [186][187][188][189][190][191]. For instance, in experiments at the Institute for Transuranium Elements in Karlsruhe using both fresh and irradiated clad samples of UO 2 and MOX at temperatures between 1700 and 2200°C, the irradiated samples dissolved to a greater extent compared to the fresh samples in the Zircaloy and dissociated into fragments during dissolution [186].…”

Section: Moalem and Olandermentioning

confidence: 99%

“…For instance, in experiments at the Institute for Transuranium Elements in Karlsruhe using both fresh and irradiated clad samples of UO 2 and MOX at temperatures between 1700 and 2200°C, the irradiated samples dissolved to a greater extent compared to the fresh samples in the Zircaloy and dissociated into fragments during dissolution [186].…”

Section: Moalem and Olandermentioning

confidence: 99%

“…For instance, porosity of $30% has been observed in high-burnup LWR fuel (53 MWd/kgU) for test temperatures of 2270 K in the presence of molten Zircaloy [185,186]. In the only in-reactor CANDU fuel test (BTF-107) to measure fuel swelling under such conditions, only modest swelling with a 10% increase in diameter occurred for the previously irradiated fuel element (6 MWd/kgU).…”

Section: Moalem and Olandermentioning

confidence: 99%

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Overview of high-temperature fuel behaviour with relevance to CANDU fuel

Lewis

Iglesias

Dickson

et al. 2009

Journal of Nuclear Materials

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Section: Moalem and Olandermentioning

confidence: 99%

Section: Moalem and Olandermentioning

confidence: 99%

Section: Moalem and Olandermentioning

confidence: 99%

Section: Moalem and Olandermentioning

confidence: 99%

See 2 more Smart Citations

Overview of high-temperature fuel behaviour with relevance to CANDU fuel

Lewis

Iglesias

Dickson

et al. 2009

Journal of Nuclear Materials

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“…For more than 30 years, numerous programmes have made it possible to make progress in this undertaking. In the framework of the European Commission EURATOM Framework Programmes (FPs) [1][2][3][4][5][6][7], the International Science and Technology Centre (ISTC)…”

Section: Introductionmentioning

confidence: 99%

Corium Experimental Thermodynamics: A Review and Some Perspectives

Barrachin

2021

Thermo

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More than 30 years ago a specialist meeting was held at Joint Research Center Ispra (Italy) from 15 to 17 January 1990 to review the current understanding of chemistry during severe accidents in light water reactors (LWR). Let us consider that, at the end of the 1980s, thermodynamics introduced in the severe accident codes was really poor. Only some equilibrium constants for a few simple reactions between stoichiometric compounds were used as well as some simple correlations giving estimates of solidus and liquidus temperatures. In the same time, the CALPHAD method was developed and was full of promise to approximate the thermodynamic properties of a complex thermochemical system by the way of a critical assessment of experimental data, a definition of a simple physical model and an optimisation procedure to define the values of the model parameters. It was evident that a nuclear thermodynamic database had to be developed with that new technique to obtain quite rapidly prominent progress in the knowledge of thermochemistry in the severe accident research area. Discussions focused on the important chemical phenomena that could occur across the wide range of conditions of a damaged nuclear plant. The most pressing need for improved chemical models is identified with condensed phase mixtures to model the corium progression. This paper reviews more than 30 years of experimental data production in the field of corium thermodynamics. This work has been conducted through multiple international programs (EURATOM, ISTC, OECD) as well as through more specific studies conducted at the national scale. This research has been capitalised in specific databases such as NUCLEA and TAF-ID, databases developed at IRSN and at CEA, respectively, and are now used in degradation models of the severe accident simulation codes. This research is presented in this paper. In the conclusion, we outline the research perspectives that need to be considered in order to address today’s and tomorrow’s issues.

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