Abstract
The procedure was developed to enable STUK to make simplified estimates on off-site consequences based on the existing results of the PSA level 2 calculations done by e.g. power utilities. Method is based on dose calculated from each nuclide group of reactor activity inventory when the same release fraction for each group is assumed.
This means that a specific new result from PSA level 2 can be categorised to find out a representative PSA level 3 result for this case. In addition a user interface including the procedure was prepared. Secondly some new insights about consequences based on the releases from PSA level 2 is expected to give better understanding of risks at prevailing increased reactor power levels. In this case only some early health effects and long-term doses were estimated without full-scope PSA level 3 approach.
This means that a specific new result from PSA level 2 can be categorised to find out a representative PSA level 3 result for this case. In addition a user interface including the procedure was prepared. Secondly some new insights about consequences based on the releases from PSA level 2 is expected to give better understanding of risks at prevailing increased reactor power levels. In this case only some early health effects and long-term doses were estimated without full-scope PSA level 3 approach.
| Original language | English |
|---|---|
| Place of Publication | Helsinki |
| Publisher | Säteilyturvakeskus |
| Number of pages | 26 |
| ISBN (Print) | 951-712-407-4 |
| Publication status | Published - 2000 |
| MoE publication type | Not Eligible |
Publication series
| Series | STUK-YTO-TR |
|---|---|
| Volume | 166 |
| ISSN | 0785-9325 |
Keywords
- PSA level 3
- risk assement
- radiation protection
- consequence assessment