Influence of corium oxidation on fission product release from molten pool

Bechta, Sevostian; Krushinov, E.V.; Vitol, S. A.; Khabensky, V.B.; Kotova, S.Yu.; Sulatsky, A. A.; Гусаров, В. В.; Al’myashev, V. I.; Ducros, G.; Journeau, Christophe; Bottomley, D.; Clément, Bernard; Herranz, L.E.; Guentay, S.; Trambauer, K.; Auvinen, Ari; Bezlepkin, V. V.

doi:10.1016/j.nucengdes.2010.01.008

Cited by 10 publications

(11 citation statements)

References 2 publications

Supporting

Mentioning

Contrasting

Unclassified

Order By: Relevance

“…The composition of the melt of experiment U55 is close to the composition of the corium studied in [3] (wt %): 72.64UO 2 ⋅ 19.38ZrO 2 ⋅ 6.15Zr. The evapora tion rate of this composition according to [3] at 2595°C was (5.3 ± 1.6) × 10 -4 g/(cm 2 s) (suboxidized corium C70). This evaporation rate in the order of magnitude and spread of the values is close to our results ( Table 2).…”

Section: Resultssupporting

confidence: 62%

“…To assess the reliability and relevance of the obtained results, we compared them with the data [3]. The composition of the melt of experiment U55 is close to the composition of the corium studied in [3] (wt %): 72.64UO 2 ⋅ 19.38ZrO 2 ⋅ 6.15Zr.…”

Section: Resultsmentioning

confidence: 90%

“…The problem of the formation of aerosols, which are the products of the evaporation and subse quent condensation of the components of complex melts, has been relatively neglected. The most thor ough study of the processes of evaporation of the main components of corium and fission products dissolved in it as a function of the oxidation potential of the melt is fulfilled for the initial corium, corresponding to the composition and temperature inside the reactor vessel in the case of a severe accident [3]. The yield of the fis sion products (primarily, iodine and cesium) in the composition of aerosols was studied in the SARNET project [4].…”

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

A study of the liquid and gaseous phases upon the interaction of molten corium with the sacrificial material based on iron oxide and Portland cement

Udalov¹,

Poznyak

Sazavsky

et al. 2016

Glass Phys Chem

View full text Add to dashboard Cite

Changes in the intensity of evaporation and the composition of condensing oxides are experimen tally studied upon diluting corium by iron(III) oxide and Portland cement. It is found that the formation rate of aerosols over the melt is reduced upon diluting the corium by the studied sacrificial material by almost an order of magnitude up to 0.5 g/(cm 2 s). In the reducing atmosphere, the form of the particles of the aerosols is octahedral and in an oxidizing atmosphere it is spherical.

show abstract

Section: Resultssupporting

confidence: 62%

Section: Resultsmentioning

confidence: 90%

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

A study of the liquid and gaseous phases upon the interaction of molten corium with the sacrificial material based on iron oxide and Portland cement

Udalov¹,

Poznyak

Sazavsky

et al. 2016

Glass Phys Chem

View full text Add to dashboard Cite

show abstract

“…Given the large horizontal area of a PHWR TDB, however, it is less likely that the top crust would be continuous, let alone crack-free. In addition, during the EVAN-1FP experiment a top crust formed but FP releases continued to be observed outside the crucible [7]. Thus, it is likely that some of the FPs released from solid or molten fuel in the TDB would make their way into the CV and into containment, despite the presence of a top crust.…”

Section: Current Modelling Of Fp Releases From a Phwr Terminal Debrismentioning

confidence: 99%

“…An extensive literature search was performed to examine national and international experiments studying FP (or simulant) releases from hot solid and molten fuel debris. Some experiments were in-core, such as the French Phébus program [6], whereas others were performed out-of-core, such as the EVAN-1FP test [7]. Lewis et al [8] summarized many of the international experimental programs and findings up to 2008, although the experimental work has continued since then.…”

Section: Literature Review and Assessment Of The Maap-candu Tdb Fp Rementioning

confidence: 99%

Fission-Product Releases From a PHWR Terminal Debris Bed

Brown

Bailey

2016

CNL Nuclear Review

View full text Add to dashboard Cite

During an unmitigated severe accident in a pressurized heavy water reactor (PHWR) with horizontal fuel channels, the core may disassemble and relocate to the bottom of the calandria vessel. The resulting heterogeneous in-vessel terminal debris bed (TDB) would likely be quenched by any remaining moderator, and some of the decay heat would be conducted through the calandria vessel shell to the surrounding reactor vault or shield tank water. As the moderator boiled off, the solid debris bed would transform into a more homogeneous molten corium pool located between top and bottom crusts. Until recently, the severe accident code MAAP-CANDU assumed that unreleased volatile and semi-volatile fission products remained in the TDB until after calandria vessel failure, due to low diffusivity through the top crust and the lack of gases or steam to flush released fission products from the debris. However, national and international experimental results indicate this assumption is unlikely; instead, high- and medium-volatility fission products would be released from a molten debris pool, and their volatility and transport should be taken into account in TDB modelling. The resulting change in the distribution of fission products within the reactor and containment, and the associated decay heat, can have significant effects upon the progression of the accident and fission-product releases to the environment. This article describes a postulated PHWR severe accident progression to generate a TDB and the effects of fission-product releases from the terminal debris, using the simple release model in the MAAP-CANDU severe accident code. It also provides insights from various experimental programs related to fission-product releases from core debris, and their applicability to the MAAP-CANDU TDB model.

show abstract

The objectives of the Phébus FP experimental programme and main findings

Clément

Zeyen

2013

Annals of Nuclear Energy

View full text Add to dashboard Cite

Influence of corium oxidation on fission product release from molten pool

Cited by 10 publications

References 2 publications

A study of the liquid and gaseous phases upon the interaction of molten corium with the sacrificial material based on iron oxide and Portland cement

A study of the liquid and gaseous phases upon the interaction of molten corium with the sacrificial material based on iron oxide and Portland cement

Fission-Product Releases From a PHWR Terminal Debris Bed

The objectives of the Phébus FP experimental programme and main findings

Contact Info

Product

Resources

About