Cooling and retention of fuel within the reactor vessel of the SNR-300 after power excursion accidents
Description
Within the framework of the licensing procedure of the SNR-300 power plant in Kalkar it is being demonstrated that the reactor vessel, the primary piping system and the in-vessel immersion cooling system withstand the mechanical loads of an energetic accident and that the functionality of the decay- heat removal chain is maintained. The basic requirements for the long-term retention of the fuel within the vessel are thus fulfilled. In the present report the heat transport from the fuel to the decay-heat removal systems are investigated for various representative fuel distributions within the reactor vessel together with the local transient temperature fields within the fuel supporting structures. It is shown that the decay heat is removed by in vessel and external natural convection flows from the fuel to the active heat sinks
Availability note (English)
Available from INIS in electronic form
Files
Additional details
Additional titles
- Original title (German)
- Kuehlung und Zurueckhaltung des Brennstoffs im Reaktortank des SNR-300 nach Exkursions-Stoerfaellen
Publishing Information
- Imprint Pagination
- 298 p.
- Report number
- IA--23.78075.2
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 37001526
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ACCIDENTS; AFTER-HEAT REMOVAL; EXCURSIONS; RHR SYSTEMS; SNR REACTOR; SODIUM COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; COOLING SYSTEMS; ENERGY SYSTEMS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; REMOVAL; SODIUM COOLED REACTORS
Optional Information
- Notes
- Refs, figs, tabs
- Secondary number(s)
- INIS-DE-IA--092