Design of a dry cask storage system for spent LWR fuels: radiation protection, subcriticality, and heat removal aspects
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O. H. Zabunoðlu
Abstract
Spent nuclear fuel resulting from reactor operation must be safely stored and managed prior to reprocessing and/or final disposal of high-level waste. Any spent fuel storage system must provide for safe receipt, handling, retrieval, and storage of spent fuel. In order to achieve the safe storage, the design should primarily provide for radiation protection, subcriticality of spent fuel, and removal of spent fuel residual heat. This article is focused on the design of a metal-shielded dry-cask storage system, which will host spent LWR fuels burned to 33000, 45000, and 55000 MWd/t U and cooled for 5 or 10 years after discharge from reactor. The storage system is analyzed by taking into account radiation protection, subcriticality, and heat-removal aspects; and appropriate designs, in accordance with the international standards.
Kurzfassung
Abgebrannte Brennelemente aus dem Betrrieb von Kernkraftwerken müssen vor einer Wiederaufarbeitung und/oder Endlagerung sicher behandelt und gelagert werden. Bei jeder Art von Lagersystem müssen Vorkehrungen für den sicheren Empfang, den Umgang, die Rückgewinnung und die Lagerung der abgebrannten Brennelemente getroffen werden. Zur sicheren Lagerung müssen bei der Auslegung Aspekte des Strahlenschutzes, der Unterkritikalität und der Abfuhr der Restwärme der abgebrannten Brennelemente berücksichtigt werden. Dieser Beitrag ist auf die Auslegung eines metallabgeschirmten Lagersystems ausgerichtet, in dem abgebrannte Brennelemente (33000, 45000, and 55000 MWd/tU) eines Leichtwasserreaktors gelagert und für 5 bis 10 Jahre gekühlt werden können. Das Lagersystem wird analysiert im Hinblick auf Aspekte des Strahlenschutzes, der Unterkritikalität und der Abfuhr der Restwärme, sowie auf eine geeignete Auslegung in Übereinstimmung mit internationalen Standards.
References
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© 2006, Carl Hanser Verlag, München
Articles in the same Issue
- 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
Articles in the same Issue
- 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
