Published December 21, 1976
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The behaviour of spherical HTR fuel elements during mass testing in the AVR reactor
Description
After a few introductory remarks on the AVR as a test reactor for fuel elements, the different variants of spherical AVR fuel elements are described. Mechanical loads, loads due to radiation, thermal, and corrosive loads on the fuel elements are investigated. The findings of the fuel element testing are presented in detail and discussed. Mass tests are best suited for fuel element testing under realistic reactor conditions. Supplementary to the mostly well-known effects of the loads during normal reactor operation, an investigation of large numbers of fuel elements may yield highly valuable statistically valid data. (UA).
Abstract (German)
Nach einigen einleitenden Bemerkungen zum AVR als Testreaktor fuer Brennelemente werden die verschiedenen Varianten von AVR-Brennelementkugeln beschrieben. Es werden die mechanischen, strahlungsbedingten, thermischen und korrosiven Belastungen der Brennelemente untersucht. Es werden die Ergebnisse der Brennelementerprobung detailliert vorgelegt und diskutiert. Massentests erlauben es am ehesten, Brennelemente unter realistischen Reaktorbedingungen zu erproben. Als Ergaenzung zu den grossenteils bekannten Effekten, die sich aus dem Reaktorbetrieb als Folge der verschiedenen Belastungen ergeben, kann die Untersuchung grosser Stueckzahlen statistisch gesicherte Aussagen von hohem Wert erbringen. (UA).
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Additional details
Additional titles
- Original title (German)
- Das Verhalten kugelfoermiger HTR-Brennelemente bei der Massenerprobung im AVR-Reaktor
Publishing Information
- Imprint Pagination
- 137 p.
- Report number
- INIS-mf--4591
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 52088232
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Thesis
- Descriptors DEI
- BURNUP; COATED FUEL PARTICLES; CONTAMINATION; CORROSION; CRACKS; FEDERAL REPUBLIC OF GERMANY; FORSCHUNGSZENTRUM JUELICH; FRACTURE PROPERTIES; FUEL ELEMENT FAILURE; FUEL ELEMENTS; HTGR TYPE REACTORS; IRRADIATION PROCEDURES; MATERIALS TESTING; MICROSTRUCTURE; NEUTRON FLUENCE; PERFORMANCE TESTING; PHYSICAL RADIATION EFFECTS; THERMAL STRESSES
- Descriptors DEC
- CHEMICAL REACTIONS; DEVELOPED COUNTRIES; EUROPE; FAILURES; FUEL PARTICLES; GAS COOLED REACTORS; GERMAN FR ORGANIZATIONS; GRAPHITE MODERATED REACTORS; MECHANICAL PROPERTIES; NATIONAL ORGANIZATIONS; RADIATION EFFECTS; REACTOR COMPONENTS; REACTORS; STRESSES; TESTING; WESTERN EUROPE
Optional Information
- Notes
- Document from Juelich Preservation Project; This record replaces 10421452