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2. Yu. G. Degal'tsev, I. S. Mosevitskii, N. N. Ponomarev-Stepnoi, et al., “Experimental studies on coolant technology and fuel elements for HTGC reactors based on PG-100 helium loops and ampule channels” in:Aspects of Nuclear Science and Engineering, Atomic Hydrogen Power Engineering and Technology Series, Issue 2 [in Russian] (1983), pp. 185–193.
3. V. N. Grebennik, “The state of research on high-temperature gas-cooled reactors in the USSR,”ibid. Aspects of Nuclear Science and Engineering, Atomic Hydrogen Power Engineering and Technology Series, Issue 2 [in Russian] (1983), pp. 106–118.
4. A. S. Chernikov, Yu. V. Koshelev, and Z. A. Shokina, “Manufacture and quality control for microelements, fuel pins, and assemblies for HTGC reactors,”ibid. Aspects of Nuclear Science and Engineering, Atomic Hydrogen Power Engineering and Technology Series, Issue 2 [in Russian], (1983), Issue 2 (1979), pp. 160–177.
5. A. O. Gol'tsev, N. E. Kukharkin, I. S. Mosevitskii, et al., “A concept for safe pressurized-water reactors containing fuel assemblies based on HTGC microelements,”At. Energ.,75, Issue 6, 418–423 (1993).