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Conference Article: In pile helium loop ''COMEDIE''

Abassin, J.J.; Blanchard, R.J.; Gentil, J. (CEA Centre d'Etudes Nucleaires de Grenoble, 38 (France))

Abstract

The SR1 test in the COMEDIE loop has permitted to demonstrate particularly the device operation reliability with a fuel loading. The post-irradiation examinations have pointed out the good filter efficiency and have enabled to determine the deposition profiles either for the activation products (e.g.: 51Cr, 60Co) or for the fission products (e.g.: 110mAg, 131I, 134Cs, 137Cs).

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key words: diagrams; engineering; filters; fission products; helium; in pile loops; radionuclide migration; siloe reactor; testing; enriched uranium reactors; information; irradiation reactors; isotope production reactors; isotopes; nonmetals; pool type reactors; radioactive materials; reactor components; reactor experimental facilitie; reactors; thermal reactors; water cooled reactors; water moderated reactors
Reference:
Specialists meeting on coolant chemistry, plate-out and decontamination in gas-cooled reactors Juelich, Federal Republic of Germany 2-4 December 1980
International Atomic Energy Agency, Vienna (Austria)
IWGGCR--2, pp:8-18