Energy-supply-independent after-heat removal in nuclear propulsion plants for ships in combination with sinking and cuntering
Creators
- 1. Hannover Univ. (Germany, F.R.). Inst. fuer Schiffsmaschinen
Description
The energy-supply-independent after-heat-removal in nuclear propulsion plants for ships in combination with sinking and cantering are analysed with a numeric simulation model. Inclination on the seaground are < 900 to the vertical. Different heat-transfer-mechanism in and out of the reactor vessel and at the structures of the containment are analysed. The computer calculation shows that in the course of the accident melting of the core at each inclination occurs. Nevertheless no melting of the reactor vessel occurs due to good cooling of the outer wall of the vessel with seawater. The accident sequenz has at inclinations of 500 to 600 to the vertical a maximum in time. (orig.)
Availability note (English)
MF available from INIS under the Report Number.Abstract (German)
Mit einem numerischen Simulationsmodell wird die fremdenergieunabhaengige Nachwaermeabfuhr aus einem Schiffsreaktor bei einer Kombination des Sinkfalls mit nachfolgender Kenterung untersucht. Es werden Kraengungswinkel < 900 beruecksichtigt. Besondere Beachtung finden dabei die unterschiedlichen Waermeuebergangsmechanismen im und am Reaktordruckbehaelter und an den Strukturen des Sicherheitseinschlusses. Die Simulationsrechnungen zeigen, dass im Verlauf des Stoerfalls der Kern des Reaktors bei jeder Schraeglage zwar schmilzt, die Reaktordruckbehaelterwand jedoch nicht durch die Kernschmelze zerstoert wird. Der Verlauf der gesamten Stoerfallsequenz weist bei mittleren Schraeglagen von 500 bis 600 ein zeitliches Maximum auf. (orig.)
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Additional details
Additional titles
- Original title (German)
- Fremdenergieunabhaengige Nachwaermeabfuhr aus Schiffskernreaktoranlagen im Sinkfall
Publishing Information
- Imprint Pagination
- 186 p.
- Report number
- GKSS--84/E/22
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 15070278
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Thesis
- Descriptors DEI
- AFTER-HEAT REMOVAL; COMPARATIVE EVALUATIONS; CONTAINMENT; COOLANT LOOPS; CORE FLOODING SYSTEMS; HEAT TRANSFER; INCIDENCE ANGLE; INCLINATION; L CODES; MELTDOWN; NATURAL CONVECTION; NS OTTO HAHN; NUCLEAR SHIPS; NUMERICAL SOLUTION; OTTO HAHN REACTOR; PRESSURE DEPENDENCE; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR ACCIDENTS; SEAWATER; SIMULATION; TEMPERATURE DEPENDENCE; TIME DEPENDENCE
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONTAINERS; CONVECTION; ECCS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; NUCLEAR MERCHANT SHIPS; OXYGEN COMPOUNDS; POWER REACTORS; PROPULSION REACTORS; REACTOR PROTECTION SYSTEMS; REACTORS; SHIP PROPULSION REACTORS; SHIPS; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- With 66 figs., 6 tabs.