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| Book/Report | FZJ-2016-05752 |
1991
Forschungszentrum Jülich GmbH Zentralbibliothek, Verlag
Jülich
Please use a persistent id in citations: http://hdl.handle.net/2128/12659
Report No.: Juel-2515
Abstract: The fission product release during normal operation from the core of a high temperature reactor is well known to be very low. For that reason in the present work a HTR-Modul-reactor with a reduced power of 170 MW$_{th}$ is examined under the aspect whether the contamination with cesium-137 as most important nuclide will be so low that a helium turbine in the primary circuit is possible. The program SPTRAN is the tool for the computations and simulation of fission product transport in high temperature reactors. The program initially developed for computations of accident events has been enlarged for computing the fission product transport under the conditions of normal operation. The theoretical basis, the used programs and data basis are presented followed by the results of the computations. These results are explained and discussed ; moreover the consequences and future possibilities of development are shown.
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