Decommissioning of reactors 1 to 5 of the Greifswald NPS (KGR)
- Kraftanlagen AG Heidelberg (Germany)
When considering the decommissioning concepts for the Greifswald NPS, two possibilities were examined: immediate demolition; and realization and maintenance of a safe enclosure for a period of 30 years. The decommissioning procedure of a reactor of the WWER 440 type differs substantially from that of a typical PWR because of the differing constructional characteristics. Only the confinement or the room system which safe-guards against overpressure provides a suitable boundary for the ``Safe Enclosure``, as this also forms a barrier to the outside. This, however, has the consequence that approximately 90% of the plant interior must be removed when achieving a safe enclosure. Because the reactor pressure vessel (RPV), which contains the main part of the radioactivity, must be dismantled and removed for both variants and this necessarily with remote controlled methods, no reduction in expenditure or time for the demolition is to be gained through a 30 year safe enclosure period. A further advantage of an ``Immediate Demolition`` is the possibility of employing a still available trained workforce and applying their expertise and knowledge of the plant to the demolition task.
- OSTI ID:
- 106248
- Report Number(s):
- CONF-930906--; ISBN 0-7918-0691-X
- Country of Publication:
- United States
- Language:
- English
Similar Records
Decommissioning concept for the thorium high-temperature reactor THTR-300
Technology, safety, and costs of decommissioning a reference pressurized water reactor power station