Radiological and thermal characteristics of CASTOR RBMK-1500 and CONSTOR RBMK-1500 casks for spent nuclear fuel storage at Ignalina Nuclear Power Plant
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P. Poskas
Abstract
The main characteristics, such as temperatures of the fuel rod cladding and cask surface, dose rates at the surface and at the some distance for CASTOR RBMK-1500 and CONSTOR RBMK-1500 casks loaded with spent nuclear fuel are presented. These casks are used for an interim dry storage of spent nuclear fuel at Ignalina Nuclear Power Plant. Numerical modeling (calculation of the equivalent dose rates, activities of nuclides, etc.) and experimental measurements of the equivalent dose and gamma spectrum on the cask surface at the dry storage facility were performed for assessment of radiation characteristics. Temperatures were evaluated using only numerical modeling. Rather good agreement between experimentally determined and calculated dose rates for CASTOR RBMK-1500 and CONSTOR RBMK-1500 casks was obtained. Also it was revealed that maximum fuel rod cladding temperature is higher for CONSTOR RBMK-1500 cask, but never exceeds the maximum allowable value. The cask surface temperatures are similar for both cask types.
Kurzfassung
Die Haupteigenschaften, wie Temperaturen des Brennstab-Mantels und der Behälter-Oberfläche, Dosisleistung an der Oberfläche und in einiger Entfernung für die mit abgebrannten Kernbrennstoffen beladenen CASTOR RBMK-1500 und CONSTOR RBMK-1500 Behälter werden vorgestellt. Diese Behälter werden für die Zwischenlagerung abgebrannter Kernbrennstoffelemente im Ignalina Kernkraftwerk verwendet. Die numerische Modellierung (Berechnung der Äquivalentdosisleistung, der Aktivität, usw.) und experimentelle Messungen der Äquivalentdosis und des Gammaspektrums auf der Behälter-Oberfläche wurden im Zwischenlager für die Strahlenschutz-Bewertung durchgeführt. Temperaturen wurden nur mit Hilfe numerischer Modellierung ausgewertet. Eine ziemlich gute Übereinstimmung zwischen experimentellen und berechneten Dosisleistungswerten für den CASTOR RBMK-1500 und den CONSTOR RBMK-1500 Behälter wurde gefunden. Außerdem wurde festgestellt, dass die maximale Temperatur des Brennstab-Mantels für den CONSTOR RBMK-1500 Behälter höher ist, aber niemals den erlaubten maximalen Wert überschreitet. Die Temperaturen der Behälter-Oberflächen sind für beide Behälter-Typen ähnlich.
References
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© 2006, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- The multipurpose thermalhydraulic test facility TOPFLOW: an overview on experimental capabilities, instrumentation and results
- Uncertainty in cross-section calculations for reactions induced by neutrons with energy above 0.1 MeV
- Determination of the exposure build-up factor in a slab using the LTSN method
- Lumped parameters analysis of the IAEA research reactor benchmark problem
- Assessment of the look-up table using the tubular and bundle CHF data and modification of the bundle correction factor
- A finite element model for static strength analysis of CANDU fuel bundle
- Effect of packing fraction variations on the multiplication factor in pebble-bed nuclear reactors
- Design of a dry cask storage system for spent LWR fuels: radiation protection, subcriticality, and heat removal aspects
- Radiological and thermal characteristics of CASTOR RBMK-1500 and CONSTOR RBMK-1500 casks for spent nuclear fuel storage at Ignalina Nuclear Power Plant
- Analyses of severe accident scenarios in RBMK-1500
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- The multipurpose thermalhydraulic test facility TOPFLOW: an overview on experimental capabilities, instrumentation and results
- Uncertainty in cross-section calculations for reactions induced by neutrons with energy above 0.1 MeV
- Determination of the exposure build-up factor in a slab using the LTSN method
- Lumped parameters analysis of the IAEA research reactor benchmark problem
- Assessment of the look-up table using the tubular and bundle CHF data and modification of the bundle correction factor
- A finite element model for static strength analysis of CANDU fuel bundle
- Effect of packing fraction variations on the multiplication factor in pebble-bed nuclear reactors
- Design of a dry cask storage system for spent LWR fuels: radiation protection, subcriticality, and heat removal aspects
- Radiological and thermal characteristics of CASTOR RBMK-1500 and CONSTOR RBMK-1500 casks for spent nuclear fuel storage at Ignalina Nuclear Power Plant
- Analyses of severe accident scenarios in RBMK-1500
