HTGR Knowledge Base
Conference Article: Transfer of fissile material through shielding coatings in emergency heating of HTGR coated particles
Gudkov, A.N.; Zhuravkov, S.G.; Koptev, M.A.; Kurepin, A.DAbstract
The measurement result s of leakage dynamics of fissile material from the coated particles within a temperature range of 12CO + 2CCOOC are given. The methods of carrying out the experiments are briefly described. The relation of the leakage rate of uraniun-235 from CF with the pyrocarbonic coatings has been obtained.
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key words: coated fuel particles; fissile materials; fuel elements; htgr type reactors; leak testing; pyrolytic carbon; reactor safety; temperature range 1000-4000 k; uranium 235
- Reference:
- Technical committee meeting on gas-cooled reactor technology safety and siting Dimitrovgrad (Russian Federation) 21-23 Jun 1989
- International Atomic Energy Agency, Vienna (Austria)
- IAEA-TC--389.26, pp:94-104
- International Atomic Energy Agency, Vienna (Austria)