Abstract
Irradiation embrittlement of the pressure vessel was found to be higher than expected in the Loviisa units after a few years of operation. The adaptive measures taken by the utility and the implemented new research programmes to support the annealing option are described. Most of the measures available to reduce the neutron dose to the pressure vessel and to soften transients in thermal shock have been taken. The amount of surveillance material, especially weld, is limited and techniques to utilize it effectively in annealing and reirradiation studies are described. The utility is prepared to anneal Unit-1 in 1996.
| Original language | English |
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| Title of host publication | International workshop on WWER-440 reactor pressure vessel embrittlement and annealing |
| Place of Publication | Vienna |
| Publisher | International Atomic Energy Agency IAEA |
| Number of pages | 11 |
| Publication status | Published - 1994 |
| MoE publication type | D3 Professional conference proceedings |
| Event | International Workshop on WWER-440 Reactor Pressure Vessel Embrittlement and Annealing - Zavazna Poruda, Slovakia Duration: 29 Mar 1994 → 31 Mar 1994 |
Conference
| Conference | International Workshop on WWER-440 Reactor Pressure Vessel Embrittlement and Annealing |
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| Country/Territory | Slovakia |
| City | Zavazna Poruda |
| Period | 29/03/94 → 31/03/94 |