Untersuchungen zu den Auswirkungen hypothetischer Störfälle bei Hochtemperaturreaktoren: Schadensumfang beim Bruch des Primärkreislaufs mit zusätzlichem Versagen aktiver Sicherheitseinrichtungen (HSK 2)
Wolters, J. (Corresponding author)
Badur, A. (Collaboration author) / David, P. H. (Collaboration author) / Fassbender, J. (Collaboration author) / Finken, R. (Collaboration author) / Haben, M. (Collaboration author) / Kasper, K. (Collaboration author) / Müller, A. (Collaboration author) / Rehm, W. (Collaboration author) / Schwarzer, K. (Collaboration author) / Talarek, H. D. (Collaboration author) / Meister, G. (Editor)
Publikationen vor 2000; PRE-2000; Retrocat
Jülich Kernforschungsanlage Jülich, Verlag 1978
89 p.
Report
Book
Addenda
Berichte der Kernforschungsanlage Jülich 1466
OpenAccess
Please use the identifier: http://hdl.handle.net/2128/11720 in citations.


The report presents the analysis of the consequences of a hypothetical accident for a nuclear power plant with a gas cooled high temperature reactor having a thermal power of 3000 MW. The HU-1160 is used as the basis for the investigation. As the initiating event a breach of the primary circuit is assumed with leak cross sections of up to 10 times the "design leak size ". The initial pressure is taken as 50 bars. For the subsequent accident sequence, failure of all plant operation systems and engineered safeguards which could counteract core heatup due to fission and fission product heat generation is supposed (rapid shut down system, main- and auxiliary core cooling systems and liner cooling system). The preservation of the structural integrity of the containment is assumed with a leakage of 0,2 vol. % per day. The analysis is carried through to the evaluation of the radiological consequences for the surroundings. A discussion of problems such as damage to the concrete pressure vessel by excessive temperatures and aspects of recriticality due to melt down of absorber rods and escape of neutron absorbing fission products is included. [...]