Air Diffusion Analysis for Experimental Set NACOK and HTR-Module
Creators
- 1. Forschungszentrum Jülich GmbH, Jülich, Germany
- 2. Tsinghua University, Beijing, China
Description
[Automatically extracted and translated] The modular high temperature gas cooled reactor is of inherent safety. In a hypothetical accident like loss of active heat sinks, the reactor will shut down automatically owing to the negative temperature feedback of the moderator, the decay heat will be transferred to the environment via passive mechanisms like heat conduction and radiation. Because of low power density of the reactor core, huge heat capacity of the reactor graphite, the peak temperature of the core is less than 1600 °C during such a severe accident, that is impossible to lead catastrophic release of the radioactivity. On the basis of the inherent safety, it is carried out a further discussion about whether the reactor is impossible to release large amount of radioactivity certainly in any situation. The discussion enhances the research of air ingress accident.
Abstract (German)
[Automatisch extrahiert und übersetzt] Der modulare Hochtemperatur-Gasgekühlte Reaktor ist von inhärenter Sicherheit. Bei einem hypothetischen Unfall wie dem Verlust aktiver Wärmesenken wird der Reaktor aufgrund des negativen Temperaturfeedbacks des Moderators automatisch heruntergefahren, die Zerfallswärme wird über passive Mechanismen wie Wärmeleitung und Strahlung an die Umgebung abgegeben. Aufgrund der geringen Leistungsdichte des Reaktorkerns und der enormen Wärmekapazität des Reaktorgrafits liegt die Spitzentemperatur des Kerns bei einem solch schweren Unfall unter 1600 °C, was einen katastrophalen Freisetzungsunfall unmöglich macht. Auf der Grundlage der inhärenten Sicherheit wird eine weitere Diskussion darüber geführt, ob der Reaktor in keiner Situation große Mengen an Radioaktivität freisetzen kann. Die Diskussion verstärkt die Forschung zum Lufteintrittsunfall.Files
ISR_IB_1993-11_ZhangZuoyi-Air Diffusion Analysis for Experimental Set NACOK and HTR-Module.pdf
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Additional details
Additional titles
- Original title (German)
- Luftdiffusionsanalyse für das Experimentierset NACOK und HTR-Modul
Publishing Information
- Report number
- KFA-ISR-IB-11/1993
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AFTER-HEAT; AFTER-HEAT REMOVAL; AIR; FEEDBACK; FISSION PRODUCT RELEASE; GRAPHITE; HTGR TYPE REACTORS; HTR REACTOR; HTR-10 REACTOR; HYPOTHETICAL ACCIDENTS; RADIOACTIVITY; REACTOR ACCIDENTS; REACTOR SAFETY; REACTOR SHUTDOWN; SEVERE ACCIDENTS; SPECIFIC HEAT
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; CARBON; ELEMENTS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FLUIDS; GAS COOLED REACTORS; GASES; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MINERALS; NONMETALS; PHYSICAL PROPERTIES; POOL TYPE REACTORS; REACTOR LIFE CYCLE; REACTORS; REMOVAL; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; SHUTDOWN; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; TRAINING REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
- Proposed descriptors and Free-text terms
- FEDERAL REPUBLIC OF GERMANY; FORSCHUNGSZENTRUM JUELICH; HTGR TYPE REACTORS;
Optional Information
- Notes
- Document from Juelich Preservation Project