Effects of ruthenium release in oxidizing conditions on a BWR source term

Atso Suopajärvi, Teemu Kärkelä, Ari Auvinen, Ilona Lindholm

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Abstract

The effect of volatile ruthenium release in a case a reference BWR nuclear plant was studied to get rough-estimates of the effects on the spreading of airborne ruthenium inside the containment and reactor building and the fission product source term. The selected accident scenario starting during shutdown conditions with pressure vessel upper head opened was a LOCA with a break in the bottom of the RPV. The results suggest that there is a remarkable amount of airborne Ru in the containment atmosphere, unlike with the standard MELCOR Ru release model which predicts no airborne Ru at all in the selected case. Based on the performed plant scoping studies it seems reasonable to take the release of volatile ruthenium oxides into account when assessing source terms for plants during shutdown states.
Original languageEnglish
Title of host publicationProceedings of the 17th International Conference on Nuclear Engineering, ICONE17
Place of PublicationNew York, NY
PublisherAmerican Society of Mechanical Engineers ASME
Pages745-749
ISBN (Print)978-079184352-9
DOIs
Publication statusPublished - 2009
MoE publication typeA4 Article in a conference publication
Event17th International Conference on Nuclear Engineering, ICONE 17 - Brussels, Belgium
Duration: 12 Jul 200916 Jul 2009

Conference

Conference17th International Conference on Nuclear Engineering, ICONE 17
CountryBelgium
CityBrussels
Period12/07/0916/07/09

Fingerprint

ruthenium
containment
accident
vessel
oxide
atmosphere
effect

Keywords

  • ruthenium
  • fission product source term
  • reactor shutdown
  • BWR

Cite this

Suopajärvi, A., Kärkelä, T., Auvinen, A., & Lindholm, I. (2009). Effects of ruthenium release in oxidizing conditions on a BWR source term. In Proceedings of the 17th International Conference on Nuclear Engineering, ICONE17 (pp. 745-749). New York, NY: American Society of Mechanical Engineers ASME. https://doi.org/10.1115/ICONE17-75946
Suopajärvi, Atso ; Kärkelä, Teemu ; Auvinen, Ari ; Lindholm, Ilona. / Effects of ruthenium release in oxidizing conditions on a BWR source term. Proceedings of the 17th International Conference on Nuclear Engineering, ICONE17. New York, NY : American Society of Mechanical Engineers ASME, 2009. pp. 745-749
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abstract = "The effect of volatile ruthenium release in a case a reference BWR nuclear plant was studied to get rough-estimates of the effects on the spreading of airborne ruthenium inside the containment and reactor building and the fission product source term. The selected accident scenario starting during shutdown conditions with pressure vessel upper head opened was a LOCA with a break in the bottom of the RPV. The results suggest that there is a remarkable amount of airborne Ru in the containment atmosphere, unlike with the standard MELCOR Ru release model which predicts no airborne Ru at all in the selected case. Based on the performed plant scoping studies it seems reasonable to take the release of volatile ruthenium oxides into account when assessing source terms for plants during shutdown states.",
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Suopajärvi, A, Kärkelä, T, Auvinen, A & Lindholm, I 2009, Effects of ruthenium release in oxidizing conditions on a BWR source term. in Proceedings of the 17th International Conference on Nuclear Engineering, ICONE17. American Society of Mechanical Engineers ASME, New York, NY, pp. 745-749, 17th International Conference on Nuclear Engineering, ICONE 17, Brussels, Belgium, 12/07/09. https://doi.org/10.1115/ICONE17-75946

Effects of ruthenium release in oxidizing conditions on a BWR source term. / Suopajärvi, Atso; Kärkelä, Teemu; Auvinen, Ari; Lindholm, Ilona.

Proceedings of the 17th International Conference on Nuclear Engineering, ICONE17. New York, NY : American Society of Mechanical Engineers ASME, 2009. p. 745-749.

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

TY - GEN

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N2 - The effect of volatile ruthenium release in a case a reference BWR nuclear plant was studied to get rough-estimates of the effects on the spreading of airborne ruthenium inside the containment and reactor building and the fission product source term. The selected accident scenario starting during shutdown conditions with pressure vessel upper head opened was a LOCA with a break in the bottom of the RPV. The results suggest that there is a remarkable amount of airborne Ru in the containment atmosphere, unlike with the standard MELCOR Ru release model which predicts no airborne Ru at all in the selected case. Based on the performed plant scoping studies it seems reasonable to take the release of volatile ruthenium oxides into account when assessing source terms for plants during shutdown states.

AB - The effect of volatile ruthenium release in a case a reference BWR nuclear plant was studied to get rough-estimates of the effects on the spreading of airborne ruthenium inside the containment and reactor building and the fission product source term. The selected accident scenario starting during shutdown conditions with pressure vessel upper head opened was a LOCA with a break in the bottom of the RPV. The results suggest that there is a remarkable amount of airborne Ru in the containment atmosphere, unlike with the standard MELCOR Ru release model which predicts no airborne Ru at all in the selected case. Based on the performed plant scoping studies it seems reasonable to take the release of volatile ruthenium oxides into account when assessing source terms for plants during shutdown states.

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Suopajärvi A, Kärkelä T, Auvinen A, Lindholm I. Effects of ruthenium release in oxidizing conditions on a BWR source term. In Proceedings of the 17th International Conference on Nuclear Engineering, ICONE17. New York, NY: American Society of Mechanical Engineers ASME. 2009. p. 745-749 https://doi.org/10.1115/ICONE17-75946