Published November 1988
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High-Temperature Reactor Module Power Plant: Safety Analysis Report: Event Flows. Chapter 6.2
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Description
Automatic translation: With the HTR module, the following events lead to an unwanted temporal increase in the reactivity of the core and the reactor power: - Incorrect extension of reflector rods or small ball cut-off elements - Intrusion of moderating substances into the core (water) - Incorrect start-up of the primary coolant throughput (over the negative temperature coefficient of reactivity) - Incorrect lowering of the cold gas temperature (above the negative temperature coefficient of reactivity) - Densification of the fuel assembly during an earthquake. Furthermore, reactivity accidents are due to the unintentional Introducing turn-off reactivity into the core.
Abstract (German)
Beim HTR-Modul führen die folgenden Ereignisse zu einem ungewollten zeitlichen Anstieg der Reaktivität des Kerns und der Reaktorleistung: - Fehlerhaftes Ausfahren von Reflektorstäben oder Kleinkugelabschaltelementen - Einbruch moderierender Substanzen in den Kern (Wasser) - Fehlerhaftes Hochfahren des Primärkühlmitteldurchsatzes (über den negativen Temperaturkoeffizienten der Reaktivität) - Fehlerhaftes Absenken der Kaltgastemperatur (über den negativen Temperaturkoeffizienten der Reaktivität) - Verdichtung der Brennelementschüttung bei einem Erdbeben. Weiterhin sind Reaktivitätsstörfälle durch das unbeabsichtigte Einbringen von Abschaltreaktivität in den Kern zu betrachten.
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Additional details
Additional titles
- Original title (German)
- Hochtemperaturreaktor-Modul-Kraftwerksanlage: Sicherheitsbericht: Ereignisabläufe. Kapitel 6.2
Publishing Information
- Imprint Pagination
- 107 p.
- Report number
- INIS-DE--22M0346
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 53061921
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- ACCIDENTS; FEDERAL REPUBLIC OF GERMANY; FORSCHUNGSZENTRUM JUELICH; FUEL ASSEMBLIES; HTGR TYPE REACTORS; POWER PLANTS; PRIMARY COOLANT CIRCUITS; SAFETY ANALYSIS; TEMPERATURE COEFFICIENT; TEMPERATURE RANGE 0400-1000 K; WATER
- Descriptors DEC
- COOLING SYSTEMS; DEVELOPED COUNTRIES; ENERGY SYSTEMS; EUROPE; GAS COOLED REACTORS; GERMAN FR ORGANIZATIONS; GRAPHITE MODERATED REACTORS; HYDROGEN COMPOUNDS; NATIONAL ORGANIZATIONS; OXYGEN COMPOUNDS; REACTIVITY COEFFICIENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; TEMPERATURE RANGE; WESTERN EUROPE
Optional Information
- Notes
- Document from Juelich Preservation Project; Figs., tabs.