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 (in German)
Technical Report
·
OSTI ID:4366021
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)
- Research Organization:
- Kernforschungsanlage, Juelich (West Germany). Institut fuer Chemische Technologie
- NSA Number:
- NSA-21-027890
- OSTI ID:
- 4366021
- Report Number(s):
- EUR--3271.d
- Country of Publication:
- Germany
- Language:
- German
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