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- W226234225 abstract "An important question in the use of coated particles as nuclear fuel carriers in high-temperature gas-cooled reactors is the extent to which gaseous and non-gaseous fission products penetrate the fuel coating. The layer of pyrolytic graphite can prevent contamination of the reactor coolant circuit by the highly radioactive fission products. Under a post-irradiation test program on the behaviour of various types of particle as a function of operating temperature, burnup, etc., a radiochemical study was made of the fission product distribution in the graphite surrounding the coated particles. For the analytic separation and assay of the fission elements distillation, precipitation, liquid-extraction and ion-exchange techniques were used. The methods are briefly described. In this way 12 fission nuclides can be determined. A notably high mobility was observed for the fission elements Ba, Sr and Y. The release of other fission products with a higher fission yield is considerably lower. Some of the parameters affecting fission product release are discussed. (auth)" @default.
- W226234225 created "2016-06-24" @default.
- W226234225 creator A5081424534 @default.
- W226234225 date "1967-07-01" @default.
- W226234225 modified "2023-09-26" @default.
- W226234225 title "Radiochemical Determination of Fission Product Release From Coated Fuel Particles After In-Pile Irradiation. RADIOCHEMISCHE BESTIMMUNG DER SPALTPRODUKTABGABE VON BESCHICHTETEN BRENNSTOFFPARTIKELN NACH DER REAKTOR-BESTRAHLUNG" @default.
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