The release of ruthenium in oxygen-rich conditions from the reactor core during a severe accident may lead to formation of significantly more volatile ruthenium oxides than produced in steam atmosphere. 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. The total release of ruthenium from the core can be 5000 times the release predicted by the standard model. 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.
Skip Nav Destination
17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4352-9
PROCEEDINGS PAPER
Effects of Ruthenium Release in Oxidizing Conditions on a BWR Source Term Available to Purchase
Atso Suopaja¨rvi,
Atso Suopaja¨rvi
VTT Technical Research Centre of Finland, Espoo, Finland
Search for other works by this author on:
Teemu Ka¨rkela¨,
Teemu Ka¨rkela¨
VTT Technical Research Centre of Finland, Espoo, Finland
Search for other works by this author on:
Ari Auvinen,
Ari Auvinen
VTT Technical Research Centre of Finland, Espoo, Finland
Search for other works by this author on:
Ilona Lindholm
Ilona Lindholm
VTT Technical Research Centre of Finland, Espoo, Finland
Search for other works by this author on:
Atso Suopaja¨rvi
VTT Technical Research Centre of Finland, Espoo, Finland
Teemu Ka¨rkela¨
VTT Technical Research Centre of Finland, Espoo, Finland
Ari Auvinen
VTT Technical Research Centre of Finland, Espoo, Finland
Ilona Lindholm
VTT Technical Research Centre of Finland, Espoo, Finland
Paper No:
ICONE17-75946, pp. 745-749; 5 pages
Published Online:
February 25, 2010
Citation
Suopaja¨rvi, A, Ka¨rkela¨, T, Auvinen, A, & Lindholm, I. "Effects of Ruthenium Release in Oxidizing Conditions on a BWR Source Term." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications. Brussels, Belgium. July 12–16, 2009. pp. 745-749. ASME. https://doi.org/10.1115/ICONE17-75946
Download citation file:
9
Views
Related Proceedings Papers
Related Articles
Research Works on Iodine and Ruthenium Behavior in Severe Accident Conditions
ASME J of Nuclear Rad Sci (April,2018)
PBMR-A Future Failsafe Gas Turbine Nuclear Power Plant?
Mechanical Engineering (August,2011)
Facts & Fission
Mechanical Engineering (December,2009)
Related Chapters
PSA Level 2 — NPP Ringhals 2 (PSAM-0156)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Lessons Learned: NRC Experience
Continuing and Changing Priorities of the ASME Boiler & Pressure Vessel Codes and Standards
Modeling of SAMG Operator Actions in Level 2 PSA (PSAM-0164)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)