Report on Work at A.E.R.E. for the Dragon Project. April - October, 1965. Dragon Project Report
Description
A report on the irradiation behaviour of this type of fuel is being published. The behaviour is assessed in terms of the four experimental techniques used for fuel study, viz. metallography, 'in-pile' gas release, 'post irradiation annealing' gas release, and solid fission product release. Results from over seventy fuel compacts examined metallographically have shown that these fuel particles withstand a wide range of irradiation conditions (temperatures 800-1600°C, burn-ups 0.2-10% fima) without any Signs of failure. At higher temperatures, 1900°C, the coating remained mechanically intact but the fuel migrated outwards through the coatings The results on solid fission product release are fewer and scattered, but , show the expected reduction in release of mobile metal products, e.g. Sr, by a factor of 10-100 compared with that from plain pyrocarbon coated particles; long-lived fission gas release from these particles (R/B values) are of the order 10-5 at 1000°C (10-4 at 1500°C). Evidence suggests, however, that the actual release from intact particles is considerably lower (10-6 at 1300°C), and that the observed release comes from approximately 1% of the particles which were broken during either fabrication or handling.
Files
Additional details
Publishing Information
- Imprint Pagination
- 14 p.
- Report number
- DP-R--397
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54030115
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COATINGS; COMPARATIVE EVALUATIONS; FEDERAL REPUBLIC OF GERMANY; FISSION PRODUCT RELEASE; FORSCHUNGSZENTRUM JUELICH; FUEL PARTICLES; HTGR TYPE REACTORS; IRRADIATION; METALS; NUCLEAR FUELS; PYROLYTIC CARBON; TEMPERATURE RANGE 0400-1000 K
- Descriptors DEC
- CARBON; DEVELOPED COUNTRIES; ELEMENTS; ENERGY SOURCES; EUROPE; EVALUATION; FUELS; GAS COOLED REACTORS; GERMAN FR ORGANIZATIONS; GRAPHITE MODERATED REACTORS; MATERIALS; NATIONAL ORGANIZATIONS; NONMETALS; REACTOR MATERIALS; REACTORS; TEMPERATURE RANGE; WESTERN EUROPE
Optional Information
- Notes
- Document from Juelich Preservation Project; tabs.