HTGR Knowledge Base
Conference Article: Neutron-physical aspects of the HTR concept with spherical fuel elements
Ponomarev-Stepnoy, N.N.; Grebennik, V.N.; Glushkov, E.S.; Kucharkin, N.EAbstract
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key words: carbon; coated fuel particles; fission product release; helium cooled reactors; htgr type reactors; reactor cores; reactor safety; reliability; specific heat; temperature coefficient
- 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:289-314
- International Atomic Energy Agency, Vienna (Austria)