Investigations on power increase of high temperature reactors with inherent safety characteristics by optimization of the core layout
Description
The HTR-module is a pebble bed reactor with excellent safety properties but with a power limitation of 200 MW(th). Starting with the module-safety concept possibilities for power increase and hereby improvement of economy of small HTR's are investigated. For this many calculations were performed and systematically analyzed, so that the following approximate formulae were developed. θmax = f (H, D, L, core geometry, loading ...). By the application of alternative core geometries as plate core, ring-shaped core, segment of ring-shaped core and cylindrical core with nozzles, also in the medium power range (≅ 1000 MW(th)) reactors can be constructed, which exclude a damage of the coated particles during an heat-up accident with depressurization (θmax ≤ 1600degC). (orig.)
Abstract (German)
Der HTR-Modul ist ein Kugelhaufenreaktor mit hervorragenden Sicherheitseigenschaften aber einer sich hieraus ergebenden Leistungsbeschraenkung von bisher 200 MWth. Ausgehend vom Modul-Sicherheitskonzept werden Moeglichkeiten zur Leistungssteigerung und damit zur Verbesserung der Wirtschaftlichkeit von kleinen HTR's untersucht. Hierzu wurden eine Vielzahl von Stoerfallrechnungen durchgefuehrt und systematisch analysiert, so dass Naeherungsformeln der folgenden Form entwickelt werden konnten. θmax = f (H, D, L, Coregeometrie, Beschickung ...). Durch den Einsatz neuartiger Coregeometrien wie Plattencore, Ringcore, Ringsegmentcore oder Nasencore lassen sich auch im mittleren Leistungsbereich (≅ 1000 MWth) Reaktoren konstruieren, die im druckentlasteten Aufheizstoerfall eine Schaedigung der Coated Particles ausschliessen (δmax ≤ 1600degC.) (orig.)
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Additional details
Additional titles
- Original title (German)
- Untersuchungen zur Leistungssteigerung von inhaerent sicheren Hochtemperaturreaktoren durch Optimierung der Coreauslegung
Publishing Information
- Imprint Pagination
- 179 p.
- Report number
- Juel--2155
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 19041841
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Thesis
- Descriptors DEI
- COMPUTERIZED SIMULATION; DEPRESSURIZATION; FLOW RATE; FLOWSHEETS; GAS FLOW; GEOMETRY; HEAT TRANSFER; HELIUM; HTGR TYPE REACTORS; MULTI-PARAMETER ANALYSIS; OPTIMIZATION; PEAKS; POWER DISTRIBUTION; REACTOR CORES; REACTOR FUELING; REACTOR SAFETY; SENSITIVITY ANALYSIS; T CODES; TEMPERATURE DEPENDENCE
- Descriptors DEC
- COMPUTER CODES; DIAGRAMS; DISTRIBUTION; ELEMENTS; ENERGY TRANSFER; FLUID FLOW; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; INFORMATION; MATHEMATICS; NONMETALS; RARE GASES; REACTOR COMPONENTS; REACTORS; SAFETY; SIMULATION; SPATIAL DISTRIBUTION