EOLO-JR: A single rod burst test programme in the ESSOR reactor
- 1. Commission of the European Communities, Ispra (Italy). Joint Research Centre
Description
From October 1979 to October 1980, six tests were performed in the EOLO-JR irradiation device in the ESSOR reactor to study the ballooning behaviour of PWR fuel rods during simulated LOCA heat-up transients. A 1m highly instrumented, internally pressurized fuel rod, running at a constant peak linear power of approx. 4kW/m, was ramped at 3K/sec from 820K to a prefixed clad temperature in the range 970 to 1080K by reducing the helium coolant flow. This temperature was maintained until clad rupture, when the reactor was scrammed. This paper summarizes the tests performed and the major results obtained. This work was executed in the framework of a contract between the Commission of the European Community (JRC-Ispra) and the Italian Government. (author)
Additional details
Publishing Information
- Imprint Title
- Specialists' meeting on fuel element performance computer modelling, Preston, United Kingdom, 15-19 March 1982
- Imprint Pagination
- 727 p.
- Journal Page Range
- p. 435-446.
- Report number
- IWGFPT--13
Conference
- Title
- Specialists' meeting on fuel element performance computer modelling.
- Dates
- 15-19 Mar 1982.
- Place
- Preston (UK).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 17007024
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- DEFORMATION; ELONGATION; EXPANSION; EXPERIMENTAL DATA; FUEL CANS; FUEL RODS; LOSS OF COOLANT; POST-IRRADIATION EXAMINATION; POWER DENSITY; PRESSURE DEPENDENCE; PWR TYPE REACTORS; RUPTURES; TEMPERATURE DISTRIBUTION; THERMAL TESTING; VERY HIGH TEMPERATURE; ZIRCALOY
- Descriptors DEC
- ACCIDENTS; ALLOYS; DATA; ENRICHED URANIUM REACTORS; FAILURES; FUEL ELEMENTS; INFORMATION; MATERIALS TESTING; NONDESTRUCTIVE TESTING; NUMERICAL DATA; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- 5 refs, 2 tabs, 6 figs.