Concept for dismantling the reactor vessel and the biological shield of the compact sodium-cooled nuclear reactor facility (KNK)
Creators
- 1. Forschungszentrum Karlsruhe (Germany)
- 2. Westinghouse Reaktor (Germany)
Description
The Compact Sodium-cooled Nuclear Reactor Facility (KNK) was an experimental nuclear power plant of 20 MW electric power erected on the premises of the Karlsruhe Research Center. The plant was initially run as KNK I with a thermal core between 1971 and 1974 and then, between 1977 and 1991, with a fast core as the KNK II fast breeder plant. Under the decommissioning concept, the plant is to be decommissioned completely to green field conditions at the end of 2005 in ten steps, i.e. under the corresponding ten decommissioning permits. To this day, nine decommissioning permits have been issued, the first one in 1993 and the most recent one, number nine, in 2001. The decommissioning and demolition activities covered by decommissioning permits 1 to 7 have been completed. Under the 8th Decommissioning Permit, the components of the primary system and the rotating reactor top shield are to be removed by late 2001. Under the 9th Decommissioning Permit, the reactor vessel with its internals, the primary shield, and the biological shield are to be dismantled. The residual sodium volume in the reactor vessel was estimated to amount to approx. 30 1. The maximum Co-60 activation is on the order of 107-108 Bq/g; the maximum dose rate in the middle of the vessel was measured in April 1997 to be 55 Sv/h. The difficulty involved especially in dismantling KNK, on the one hand, is posed by the residual sodium in the plant, which determines the choice of neither wet nor thermical techniques to be used in disassembly. Another difficulty is caused by the depth of activation by fast neutrons, as a result of which not only the reactor vessel proper, but also the entire primary shield (60 cm of grey cast iron) and large parts of the biological shield must be disassembled and disposed of under remote control. (author)
Additional details
Publishing Information
- Imprint Title
- Technical meeting on 'Operational and decommissioning experience with fast reactors'. Working material
- Imprint Pagination
- 780 p.
- Journal Page Range
- p. 524-531
- Report number
- IAEA-TM--25332
Conference
- Title
- IAEA-TWGFR technical meeting on 'Operational and decommissioning experience with fast reactors'
- Dates
- 11-15 Mar 2002
- Place
- Cadarache (France)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 34029242
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACTIVITY LEVELS; BIOLOGICAL SHIELDS; CAST IRON; KNK-2 REACTOR; LICENSING PROCEDURES; PLANNING; REACTOR DECOMMISSIONING; REACTOR DISMANTLING; REACTOR VESSELS; REMOTE CONTROL
- Descriptors DEC
- ADMINISTRATIVE PROCEDURES; ALLOYS; CARBON ADDITIONS; CONTAINERS; CONTROL; DECOMMISSIONING; DEMOLITION; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; HYDRIDE MODERATED REACTORS; IRON ALLOYS; IRON BASE ALLOYS; LIQUID METAL COOLED REACTORS; POWER REACTORS; REACTORS; RESEARCH AND TEST REACTORS; SHIELDS; SILICON ALLOYS; SODIUM COOLED REACTORS; SZR TYPE REACTORS; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 4 figs, 2 tabs
- Secondary number(s)
- TWG-FR--109