Methods and data for HTGR fuel performance and radionuclide release modeling during normal operation and accidents for safety analysis
Methods and data for HTGR fuel performance and radionuclide release modeling during normal operation and accidents for safety analysis
The previous status report released in 1987 on reference data and calculation models for fission product transport in High-Temperature, Gas-Cooled Reactor (HTGR) safety analyses has been updated to reflect the current state of knowledge in the German HTGR program. The content of the status report ha...
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Personal Name(s): | Verfondern, Karl |
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Martin, R. C. / Moormann, R. | |
Contributing Institute: |
Publikationen vor 2000; PRE-2000; Retrocat |
Imprint: |
Jülich
Forschungszentrum Jülich GmbH Zentralbibliothek, Verlag
1993
|
Physical Description: |
VI, 161 p. |
Document Type: |
Report |
Research Program: |
Addenda |
Series Title: |
Berichte des Forschungszentrums Jülich
2721 |
Link: |
OpenAccess |
Publikationsportal JuSER |
The previous status report released in 1987 on reference data and calculation models for fission product transport in High-Temperature, Gas-Cooled Reactor (HTGR) safety analyses has been updated to reflect the current state of knowledge in the German HTGR program. The content of the status report has been expanded to include information from other national programs in HTGRs to provide comparative information on methods of analysis and the underlying database for fuel performance and fission product transport. The release and transport of fission products during normal operating conditions and during the accident scenarios of core heatup, water and air ingress, and depressurization are discussed. |