Coupled calculation of the radiological release and the thermal-hydraulic behavior of a 3-loop PWR after a SGTR by means of the code RELAP5 [electronic resource]
To enable a more realistic and accurate calculation of the radiological consequences of a SGTR, a fission product transport model was developed. As the radiological releases strongly depend on the thermal-hydraulic transient, the model was included in the RELAP5 input decks of the Belgian NPPs. This...
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Online Access (via OSTI) |
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| Format: | Government Document Electronic eBook |
| Language: | English |
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Rockville, Md. : Oak Ridge, Tenn. :
U.S. Nuclear Regulatory Commission ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
1995.
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| Subjects: |
Internet
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| Call Number: |
E 1.99: conf-950904--vol.4
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| E 1.99: conf-950904--vol.4 | Available |