Sicherheitstechnische Untersuchungen zum Störfallverhalten des HTR-500
Sicherheitstechnische Untersuchungen zum Störfallverhalten des HTR-500
Safety related studies on the accident behaviour of the HTR-500 comprised a total of 8 subsections on HTR safety and served the purpose of making an initial statement about the risk to be expected from this plant concept. The major emphasis of these studies was on accidents with failure of the force...
Saved in:
Personal Name(s): | Altes, J. |
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Breitbach, G. / David, P. H. / Degen, G. / Fassbender, J. / Finken, R. / Haben, M. / Jahn, W. / Katscher, W. / Kröger, W. / Mertens, J. / Mohr, H. G. / Moormann, R. / Rehm, W. / Schwarzer, K. / Verfondern, K. / Wolters, J. / Nabbi, Rahim (Editor) | |
Contributing Institute: |
Publikationen vor 2000; PRE-2000; Retrocat |
Imprint: |
Jülich
Kernforschungsanlage Jülich GmbH Zentralbibliothek, Verlag
1984
|
Physical Description: |
IV, 217 p. |
Document Type: |
Report Book |
Research Program: |
ohne Topic |
Series Title: |
Spezielle Berichte der Kernforschungsanlage Jülich
240 |
Link: |
OpenAccess |
Publikationsportal JuSER |
Safety related studies on the accident behaviour of the HTR-500 comprised a total of 8 subsections on HTR safety and served the purpose of making an initial statement about the risk to be expected from this plant concept. The major emphasis of these studies was on accidents with failure of the forced core cooling, so-called core heat-up accidents,because they determine the risk of an HTR of this power size. A mean frequency of approx. 10$^{-4}$ /a was determined for core heat-up accidents; however, in more than 90 % of these cases the reactor pressure vessel only opens momentarily. Only in 1 $^{0}$/00 of the cases the integrity of the pressure vessel liner is lost by additional failure of the liner cooling system and radioactivity is relased into the environment without passing the filters. By failure of the forced cooling system the maximum core temperatures rise to 1700 °C in the pressurized reactor and up to 2550 °C in a depressurized reactor. In either case, however, only a few percent of the core volume are affected. Only in the second case the mean core temperature slightly exceeds the value of 1600 °C, the beginning of increased failure of the fuel particle coating. Core cooling can be restored within 10 h without thermally overloading the cooling systems. Failure of the liner cooling system as a consequence of a core heat-up can be ruled out. Consequently the integrity of the reactor pressure vessel liner is maintained with a functioning liner cooling system. Moreover, the liner cooling system prevents damage within the reactor pressure vessel which could aggravate the accident. Long-term failure of the liner cooling leads to serious core damage after about 4 days and to destruction of the liner and decomposition of the adjoining concrete after more than one week. [...] |