Fuel elements based on spherical fuel pellets with a protective coating for enhanced-safety reactors

Atomic Energy

Volumn 87, Issue 6, 1999, Pages 871-883

  Chernikov, A S ^a   Permyakov, L N ^a   Fedik, I I ^a   Gavrilin, S S ^a   Kurbakov, S D ^a  

^a NONE

Author keywords

[No Author keywords available]

Indexed keywords

EID: 0039729925     PISSN: 10634258     EISSN: None     Source Type: Journal    
DOI: 10.1007/BF02673541     Document Type: Article

References (43)

1. A. G. Samoilov, A. I. Kashtanov, and V. S. Volkov, Dispersion Fuel Elements. Vol. 2. Construction and Working Capacity [in Russian], Énergoatomizdat, Moscow (1982).
2. R. B. Kotel'nikov, S. N. Bashlykov, A. I. Kashtanov, and T. S. Men'shikova, High-Temperature Nuclear Fuel [in Russian], Atomizdat, Moscow (1978), 2nd edition.
3. D. Bedenig, Gas-Cooled High-Temperature Reactors [Russian translation], Atomizdat, Moscow (1975).
4. A. Holden, Dispersion Fuel Element, Gordon and Breach, New York (1967).
5. L. Cope, "The mechanical properties of nuclear cermets," Metallurgia, 72, No. 432, 165-177 (1965).
6. P. Weimar, F. Thümmler, and H. Bumm, "Cermets with idealized structure obtained by particles coating and HIP," J. Nucl. Mater., 3, 215-225 (1969).
7. L. N. Permyakov, A. S. Chernikov, S. S. Gavrilin, et al., "Cermet-core matrix-type fuel elements for water-moderated water-cooled enhanced-safety power reactors," in: Reports at the 3rd Interdepartmental Conference on Reactor Materials Engineering [in Russian], NIIAR, Dimitrovgrad (1994), Vol. 1, pp. 134-143.
8. V. Popov, A. Ryshkov, V. Troyanov, et al., "A cermet fuel application for PWR safety improvement," in: Proceedings of the International Conference on the Design and Safety of Advanced Nuclear Power Plants, Tokyo (1992), Vol. 2, pp. 7.7.1-7.7.4.
9. A. S. Chernikov, L. N. Permyakov, S. S. Gavrilin, et al., "Fuel element with cermet fuel of matrix type for VVÉRs of advanced safety," in: The 7th International Conference on Emerging Nuclear Energy Systems ICENES-93, Japan, September 20-24, 1993, pp. 283-286.
10. A. S. Chernikov, L. N. Permyakov, and S. S. Gavrilin, "Cermet fuel elements for VVÉRs," in: Proceedings of ARS' 94 International Topical Meeting on Advanced Reactor Safety, American Nuclear Society, Pittsburg, April 1994, Vol. 2, pp. 1097-1101.
11. A. N. Protsenko and I. G. Belousov, "Basic requirements for nuclear sources of energy for technological production and high-temperature nuclear reactors," Vopr. Atom. Nauki Tekh., Ser. Atomno-Vodorodnaya Énerg. Tekh., No. 3, 5-7 (1980).
12. A. S. Chernikov, N. N. Ponomarev-Stepnoi, Yu. V. Koshelev, et al., "Spherical fuel elements for HTGR reactors and some results of tests of the fuel elements," Vopr. Atom. Nauki Tekh., Ser. Atomno-Vodorodnaya Énerg. Tekh., No. 7, 185-194 (1986).
13. V. N. Grebennik, Yu. D. Degal'tsev, N. N. Ponomarev-Stepnoy, et al., "Analysis and choice of characteristics of the HTGR spherical fuel elements (Analysis and choice of characteristic of HTGR spherical fuel elements," in: Special Meeting on Gas-Cooled Reactor Fuel Development and Spent Fuel Treatment, Moscow, October 18-21, 1983, IAEA, IWGGR/8 (1985), pp. 5-18.
14. V. S. Eremeev, V. S. Kolesov, and A. S. Chernikov, "The calculation-experimental investigation of the HTGR fuel element construction," ibid., pp. 66-78.
15. K. Röllig and W. Theymann, "Operational requirements of spherical HTR fuel elements and their performance," ibid., pp. 19-32.
16. A. S. Chernikov, "HTGR fuel and fuel elements," At. Énerg., 65, No. 1, 32-38 (1988).
17. A. S. Chernikov, V. S. Kolesov, L. N. Permyakov, et al., "Construction and basic characteristics of HTGR fuel elements," in: Proceedings of a Technical Committee on Gas-Cooled Reactors, Minsk, USSR, October 12-16, 1981. IAEA-TechDoc-275 (1983), pp. 371-381.
18. A. S. Chernikov, L. N. Permyakov, L. I. Mikhailichenko, and S. D. Kurbakov, "Characteristics of HTGR spherical fuel elements," in: Reports at a Meeting of the Technical Committee of IAEA on Gas-Cooled Reactors and Their Applications, Zurich, October 20-23, 1986.
19. A. S. Chernikov, L. N. Permyakov, L. I. Mihailichenko, and A. A. Kuznetsov, "Spherical coated particle fuel for fuel elements of HTGR," in: Special Meeting on Gas-Cooled Reactor Fuel Development and Spent Fuel Treatment, Moscow, October 18-21, 1983, IAEA, IWGGR/8 (1985), pp. 113-132.
20. A. S. Chernikov, Yu. V. Koshelev, L. I. Mihailichenko, and S. D. Kurbukov, "HTGR spherical elements and their experimental development," ibid., pp. 113-132.
21. A. S. Chernikov, N. A. Landin, E. K. Lysenko, and A. P. Gudovich, "Spherical microfuel for HTGR. Some structural features," At. Énerg., 67, No. 6, 381-389 (1989).
22. T. A. Sazykina and N. I. Tikhonov, "Computational investigation of the stress-strain state and ways to choose an optimal construction of fuel microelement for high-temperature gas-cooled reactor," Vopr. Atom. Nauki Tekh., Ser. Atomno-Vodorodnaya Énerg. Tekhn., No. 3(16), 74-76 (1983).
23. A. S. Chernikov, L. I. Mikhailichenko, G. V. Orlov, and S. D. Kurbakov, "HTGR fuel microelements. Properties of coating materials and results of prereactor tests," At. Énerg., 68, No. 3, 181-186 (1990).
24. V. G. Baturin, F. M. Zelenyuk, V. N. Kruglov, et al., "Investigation of pyrolytic carbon coatings of HTGR fuel microelements by neutron and x-ray diffraction methods," ibid., 70, No. 3, 151-156 (1991).
25. S. D. Kurbakov, A. S. Chernikov, and V. V. Teslenko, "Effect of the surface area of a fluidized bed on the deposition rate of pyrolytic carbon," Zh. Prikl. Khim., No. 7, 1589-1590 (1990).
26. A. S. Chernikov, L. I. Mikhailichenko, "Matrix graphite HTGR fuel elements. Fabrication variants. Properties. Radiation behavior," At. Énerg., 72, No. 4, 360-366 (1992).
27. N. N. Ponomarev-Stepnoy and A. A. Khrulev, "Release of fission products from high temperature fuel materials," in: Proceedings of the III International Conference on Thermoionic Energy, Julich, Germany (1972).
28. N. N. Ponomarev-Stepnoy, A. A. Khrulev, G. V. Momt, et al., "Fuel microelements and fuel elements studies with the use of preirradiation," in: Special Meeting on Gas-Cooled Reactor Fuel Development and Spent Fuel Treatment, Moscow, October 18-21, 1983, IAEA, IWGGR/8 (1985), pp. 212-225.
29. A. S. Chernikov, V. S. Kolesov, and A. I. Deryugin, "In-pile test of HTGR fuel particles and fuel elements," in: Special Meeting on Fission Products Release and Transport in Gas-Cooled Reactors, Berkeley, UK, October 22-25, 1985. IAEA, IWGGCR/13, pp. 74-80.
30. A. I. Deryugin, A. S. Chernikov, G. V. Momot, et al., "Behavior of HTGR fuel microelements and fuel elements in tests under normal and accident conditions," At. Énerg., 73, No. 3, 189-195 (1992).
31. V. A. Gurin, Yu. G. Degal'tsev, N. N. Pnomarev-Stepnoy, et al., "Reactor tests of spherical fuel elements and HTGR fuel microelements and study of their state after irradiation," in: Special Meeting on Gas-Cooled Reactor Fuel Development and Spent Fuel Treatment, Moscow, October 18-21, 1983, IAEA, IWGGR/8 (1985), pp. 5-18.
32. V. S. Eremeev, A. S. Chernikov, S. P. Kravtsov, et al., "Damage susceptibility of HTGR spherical fuel elements during short-time high-temperature action under IGR reactor conditions," At. Énerg., 72, No. 3, 298-301 (1992).
33. 4 dissociating coolant," in: Special Meeting on Gas-Cooled Reactor Fuel Development and Spent Fuel Treatment, Moscow, October 18-21, 1983, IAEA, IWGGR/8 (1985), pp. 56-65.
34. S. S. Gavrilin, L. N. Permyakov, and A. S. Chernikov, "Development of cermet nuclear fuel with prescribed properties," in: Fourth Departmental Conference on "Nuclear Power in Space. Materials. Fuel," Moscow (1993), p. 95.
35. L. N. Permyakov, S. S. Gavrilin, A. A. Antonov, et al., "Zirconium-aluminum alloys as a cermet composition matrix," in: Advances in Powder Metallurgy and Particulate Materials - 1996, MPIF, Princeton (1996), p. 13.
36. L. N. Permyakov, S. S. Gavrilin, M. S. Pirogov, et al., "Investigation of the possibility of using Zr-Al and Nb-Al alloys as a material for the matrix of cermet fuel elements," in: 3rd Interdepartmental Conference on Reactor Material Science [in Russian], Dimitrovgrad (1994), Vol. 1, pp. 144-154.
37. L. N. Permyakov, A. A. Antonov, V. P. Isakov, and S. T. Shchetnikova, "Corrosion fracture of cermet in an oxidative medium," At. Énerg., 75, No. 2, 92-97 (1993).
38. A. S. Chernikov, V. P. Isakov, A. A. Antonov, et al., "Effect of mechanical stresses on corrosion behavior of the jacket and core of BRIG-300 fuel element in a nitrogen tetraoxide medium," in: Proceedings of a Technical Committee on Gas-Cooled Reactors, Minsk, USSR, October 12-16, 1981. IAEA-TechDoc-275 (1983), pp. 383-396.
39. L. N. Permyakov, M. S. Pirogov, V. D. Potechin, et al., "The structure of cermets manufactured by hot pressure impulse methods," in: Advances in Powder Metallurgy and Particulate Materials-1992, MPIF, Princeton (1992), Vol. 8, pp. 299-306.
40. L. N. Permyakov, L. A. Izhvanov, and V. A. Strykanov, "Method for fabricating calcinated parts," Inventor's Certificate No. 445526 (USSR), Priority November 3, 1972; Byull. Izobret., No. 37, 35 (1974).
41. L. N. Permyakov, L. A. Izhvanov, and V. A. Strykanov, "Method for fabricating calcinated parts," Inventor's Certificate No. 445526 (USSR), Priority November 3, 1972; Byull. Izobret., No. 37, 35 (1974).
42. S. S. Gavrilin, L. N. Permyakov, and A. S. Chernikov, "Composite material for fuel cores for dispersion fuel elements," Patent of the Russian Federation - Claim. No. 98112373/25(013488), Priority dating from June 23, 1998.
43. N. N. Egorov, N. I. Ermakov, N. N. Ponomarev-Stepnoy, et al., "Characteristic features of HTGR fuel cycle utilizing weapons plutonium," in: Report at the 5th International Conference on Reprocessing, Conditions of Enrichment and Storage RECOD' 98, October 25-28, 1999, France.