High-Temperature Irradiation Experiments on Plutonium-Bearing Coated Particle Fuel
- 1. OECD High Temperature Reactor Project (Dragon), Winfrith, Dorset (United Kingdom)
- 2. Danish A.E.K. , Risø, Roskilde (Denmark)
- 3. AB Atomenergi, Studsvik (Sweden)
Description
Plutonium-bearing coated particle fuel is being developed by the Dragon Project for use as a feed fuel in a feed and breed system for high-temperature reactors. To demonstrate the feasibility of irradiating this type of fuel in the Dragon Reactor a series of irradiation experiments on small representative fuel specimens have been conducted in purged capsule reactor loops at Studsvik, Sweden. These fuels have operated satisfactorily up to 37% fifa burn-up at temperatures in the reactor-operating range of 1200 to 1450°C at present envisaged, as well as up to 20% fifa burn-up at temperatures of 1850°C which represent credible accident conditions. Particular attention has been paid to the measurement of the release rates of fission products of importance in high-temperature reactor technology as well as to the possible release of plutonium from the fuel which under reactor conditions might lead to contamination of the primary coolant circuit. With fuel temperatures of 1450°C the highest release fractions measured were for 133Xe and 85mKr, and were about 5 X 10-5. Maximum release fractions for short-lived gases were in the region of 1 x 10-1. With fuel temperatures of 1850°C the release fractions o 133Xe were in the region of 10-2 . Solid fission product releases were at worst two orders of magnitude less than 133Xe. No evidence of plutonium release from the coated particles was detected in post-irradiation examination gamma-ray spectrometry. Post-irradiation metallographic examination showed excellent mechanical behaviour of the particles. (author)
Additional details
Publishing Information
- Publisher
- IAEA
- Imprint Place
- Vienna (International Atomic Energy Agency (IAEA))
- Imprint Title
- Plutonium as a Reactor Fuel. Proceedings of a Symposium on the Use of Plutonium as a Reactor Fuel
- Imprint Pagination
- 876 p.
- Series
- Proceedings Series
- Journal Page Range
- p. 391-416
- ISSN
- 0074-1884
Conference
- Title
- Symposium on the Use of Plutonium as a Reactor Fuel
- Dates
- 13-17 Mar 1967
- Place
- Brussels (Belgium)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 44073761
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DRAGON REACTOR; FISSION PRODUCT RELEASE; IRRADIATION; KRYPTON 85; METALLOGRAPHY; NUCLEAR FUELS; PLUTONIUM; POST-IRRADIATION EXAMINATION; PRIMARY COOLANT CIRCUITS; R-2 REACTOR; REACTOR TECHNOLOGY; TEMPERATURE RANGE 1000-4000 K; XENON 133
- Descriptors DEC
- ACTINIDES; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; COOLING SYSTEMS; DAYS LIVING RADIOISOTOPES; ELEMENTS; ENERGY SOURCES; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; EVEN-ODD NUCLEI; EXPERIMENTAL REACTORS; FUELS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HOURS LIVING RADIOISOTOPES; HTGR TYPE REACTORS; INTERMEDIATE MASS NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; IRRADIATION REACTORS; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; KRYPTON ISOTOPES; MATERIALS; MATERIALS TESTING REACTORS; METALS; MICROSECONDS LIVING RADIOISOTOPES; NUCLEI; POWER REACTORS; RADIOISOTOPES; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; TEMPERATURE RANGE; THERMAL REACTORS; THORIUM REACTORS; TRANSURANIUM ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS; XENON ISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 7 refs., 9 tabs., 11 figs.
- Secondary number(s)
- IAEA-SM--88/38