The ASTEC Integral Code for Severe Accident Simulation

Dorsselaere, J.P. Van; Séropian, C.; Chatelard, P.; Jacq, F.; Fleurot, J.; Giordano, P.; Reinke, N.; Schwinges, B.; Allelein, Hans-Josef; Luther, W.

doi:10.13182/nt09-a4102

Cited by 102 publications

(42 citation statements)

References 7 publications

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“…It has been applied to serial analyses of experiments, severe accident sequences, and evaluation of designs. The code ASTEC is a joint research product of GRS (Germany) and IRSN (France) to simulate severe accidents (Van Dorsselaere et al, 2009;Coindreau et al, 2010;Dorsselaere et al, 2012;Chatelard et al, 2014). It is a relatively new and integrated code designed to predict all the behaviors during severe accidents in LWRs, such as any event in the beginning and any event with possible radiation related to a certain fission product.…”

Section: Code Development Review and Relevant Applicationsmentioning

confidence: 99%

“…Some of the experiments focus directly on core degradation and material migration phenomenon (Hagen et al, 1996;Hofmann FigURe 1 | Core melting of AP1000 (Zhang et al, 2015a,b Repetto et al, 2003;Van Dorsselaere et al, 2006), while other experiments deal with separate effects testing of core degradation and material migration phenomenon (Thomsen, 1998;Steinbrück et al, 2010). Next, this paper comes to the numerical investigation and code development of core degradation and material migration (Vierow et al, 2004;Van Dorsselaere et al, 2009). The physical models are reviewed and compared with provide references for relevant research.…”

mentioning

confidence: 99%

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Review on Core Degradation and Material Migration Research in Light-Water Reactors

Wang

Shi

et al. 2018

Front. Energy Res.

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Section: Code Development Review and Relevant Applicationsmentioning

confidence: 99%

mentioning

confidence: 99%

Review on Core Degradation and Material Migration Research in Light-Water Reactors

Wang

Shi

et al. 2018

Front. Energy Res.

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“…moDEliAVimo mEtoDiKA aSteC (angl. Accident Source Term Evaluation Code) [10] programų paketas buvo sukurtas bendradarbiaujant Prancūzijos irSn (pranc. Institut de Radioprotection et de Sûreté Nucléaire) ir Vokietijos grS (vok.…”

Section: Quench-3 Eksperimento Aprašymasunclassified

QUENCH-3 eksperimento modeliavimas ASTEC programų paketu

Šutas¹,

Кaliatka²,

Vileiniškis³

2015

energetika

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Lietuvos energetikos institutas, Branduolinių įrenginių saugos laboratorija, Breslaujos g. 3, Algirdas.Kaliatka@lei.lt, Virginijus.Vileiniskis@lei.lt Pasaulio mokslininkai jau daugelį metų atlieka eksperimentinių procesų, vykstančių avariniu būdu aušinant branduolinio reaktoriaus aktyviąją zoną, tyrimus bei modeliuoja juos įvairiais programų paketais. Straipsnyje pateikiami QUenCH-3 eksperimento modeliavimo rezultatai, jų palyginimas su žinomais eksperimento duomenimis bei modeliavimo parametrų įtaka modeliavimo rezultatams. Modeliavimas buvo atliktas aSteC programų paketo iCare moduliu, varijuojant kaitinimo elementų papildomą kontaktų varžą, cirkonio dioksido savitąją šilumą ir šiluminį laidumą bei patiekiamo aušinančiojo vandens kiekį. Modeliuojant buvo analizuojami eksperimentinio stendo elementų temperatūros kitimas bei bendras eksperimento metu susidarančio vandenilio kiekis. nustatyta, jog apskaičiuotos kuro rinklės imitatoriaus temperatūros pakankamai gerai atitinka eksperimentinius rezultatus. tačiau eksperimento metu susidarančio vandenilio kiekis dvigubai viršija modeliavimo metu apskaičiuotą vandenilio kiekį. tai rodo, kad turima programų paketo versija nėra pritaikyta modeliuoti cirkonio oksidaciją, kai kuro rinklės yra smarkiai pažeis-tos. Didžiausią įtaką eksperimento modeliavimo rezultatams turi kaitinimo elementų papildomos kontaktinės varžos keitimas.Raktažodžiai: QUenCH-3 eksperimentas, aSteC programų paketas, kuro rinklė, cirkonio oksidacija ĮVADAS avarijos branduolinėje jėgainėje atveju, net ir sustabdžius grandininę reakciją branduoliniame reaktoriuje, labai svarbu užtikrinti pakankamą aktyviosios zonos aušinimą. aktyviąją zoną sudaro branduolinio kuro rinklės, susidedančios iš kuro strypų. kuro strypas -tai cirkonio lydinio hermetiškas vamzdelis, kuriame patalpintos branduolinio kuro (urano dioksido) tabletės. Šis užsandarintas vamzdelis (kuro strypo sudedamoji dalis) vadinamas apvalkalu. Dėl liekamosios šilumos išsiskyrimo branduolinio kuro tabletėse po reaktoriaus sustabdymo pagrindinių avarinio aušinimo sistemų veiklos sutrikimas gali tapti sunkiosios avarijos priežastimi. Jei reaktoriaus aktyvioji zona nepakankamai aušinama, kuro strypų temperatūra pradeda kilti. kai pasiekiama ~1100 k temperatūra, kuro strypų apvalkalai tampa plastiški ir pradeda deformuotis. temperatūrai perkopus 2000 k, šie cirkonio lydinio apvalkalai pradeda lydytis, susidaro urano oksido ir išsilydžiusio cirkonio eutektika. Urano dioksido tablečių lydymosi temperatūra -~3100 k. kai

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“…For numerical approach of core degradation, integral codes (MAAP4 [8], MELCOR [9] or ASTEC [13]) use Cartesian grid(s) and discretization on these grids to compute physical properties evolution of the core associated. A liquid phase corresponding to corium is represented as volume fractions or cell type on the core grid (information on the degradation state of the cell).…”

Section: Introductionmentioning

confidence: 99%

“…This tool is based on a simplified physical modelling and the experience gained on the LEONAR code [14]. This framework is focused only on the corium propagation: no fission products and hydrogen releases are modeled as in the integral codes [8,9,13]. The use of simplified models allows propagating the uncertainties on the data or on the modeling by using a statistical tool [15] which is based on a Monte-Carlo method.…”

Section: Introductionmentioning

confidence: 99%

A simplified geometrical model for transient corium propagation in core for LWR with heavy reflector

Saas

Tellier

Bajard

2017

EPJ Nuclear Sci. Technol.

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Abstract. In the context of the simulation of the Severe Accidents (SA) in Light Water Reactors (LWR), we are interested on the in-core corium pool propagation transient in order to evaluate the corium relocation in the vessel lower head. The goal is to characterize the corium and debris flows from the core to accurately evaluate the corium pool propagation transient in the lower head and so the associated risk of vessel failure. In the case of LWR with heavy reflector, to evaluate the corium relocation into the lower head, we have to study the risk associated with focusing effect and the possibility to stabilize laterally the corium in core with a flooded down-comer. It is necessary to characterize the core degradation and the stratification of the corium pool that is formed in core. We assume that the core degradation until the corium pool formation and the corium pool propagation could be modeled separately. In this document, we present a simplified geometrical model (0D model) for the in-core corium propagation transient. A degraded core with a formed corium pool is used as an initial state. This state can be obtained from a simulation computed with an integral code. This model does not use a grid for the core as integral codes do. Geometrical shapes and 0D models are associated with the corium pool and the other components of the degraded core (debris, heavy reflector, core plate . . . ). During the transient, these shapes evolve taking into account the thermal and stratification behavior of the corium pool and the melting of the core surrounding components. Some results corresponding to the corium pool propagation in core transients obtained with this model on a LWR with a heavy reflector are given and compared to grid approach of the integral codes MAAP4.

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The ASTEC Integral Code for Severe Accident Simulation

Cited by 102 publications

References 7 publications

Review on Core Degradation and Material Migration Research in Light-Water Reactors

Review on Core Degradation and Material Migration Research in Light-Water Reactors

QUENCH-3 eksperimento modeliavimas ASTEC programų paketu

A simplified geometrical model for transient corium propagation in core for LWR with heavy reflector

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