Mononitride fuel for fast reactors

Atomic Energy

Volumn 95, Issue 3, 2003, Pages 624-636

  Rogozkin, B D ^a   Stepennova, N M ^a   Proshkin, A A ^b  

^a Federal State Unitary Enterprise   (Russian Federation)

^b KURCHATOV INSTITUTE   (Russian Federation)

Author keywords

[No Author keywords available]

Indexed keywords

FUEL CYCLES; MONONITRIDES; NUCLEAR WEAPONS;

FAST REACTORS; NEUTRONS; NUCLEAR FUEL CLADDING; PLUTONIUM; RADIOACTIVE WASTES; RADIOACTIVITY; URANIUM;

NUCLEAR FUELS;

EID: 0348216482     PISSN: 10634258     EISSN: None     Source Type: Journal    
DOI: 10.1023/B:ATEN.0000007886.86817.32     Document Type: Article

References (63)

1. V. V. Orlov, "Pu disposal and burning in lead-cooled fast reactor," in: Techn. Comm. on Unconventional Options for Pu Disposition, November 7-10, 1994, Obninsk, Russia, IAEA-TECDOC-840, November 1995.
2. B. D. Rogozkin, V. V. Orlov, A. G. Sila-Novitsky, et al., "Properties and synthesis and reprocessing technology mononitride fuel for inherently safe reactors," in: ARS'94 International Topical Meeting Advanced Reactors Safety, Pittsburgh, USA, April 17-21, 1994.
3. V. V. Orlov, E. N. Avrorin, O. E. Adamov, et al., "Unconventional concepts for inherently safe nuclear power plants," At. Énerg., 72, No. 4, 317-328 (1992).
4. E. O. Adamov (ed.), White Book of Nuclear Power, Moscow (2001).
5. Yu. E. Bagdasarov, V. M. Poplavskii, V. I. Matveev, et al., "Inherent safety of a promising nuclear technology based on BN-800," At. Énerg., 90, No. 6, 438-444 (2001).
6. B. D. Rogozkin, Yu. K. Bibilashvily, F. G. Reshetnikov, et al., "Production and studies of U and Pu nitrides as nuclear fuel and forms of weapon grade plutonium storage," in: Global-95, France, September 11-14, 1995, Vol. 2, pp. 1359-1366.
7. H. Blank, "Specification and characterization of dense fuels for liquid metal cooled fast breeder reactors," J. Nucl. Mater., 153, No. 2, 171-177 (1988).
8. A. Bauer, "Nitride fuels: properties and potentials," J. Nucl. Techn., 15, No. 2, 87-104 (1972).
9. A. Bauer and J. Brown, "Mixed-nitride fuel irradiation performance," in: Proceedings of ANS Conference on Fast Reactor Fuel Element Technology, New Orleans, USA, April 13-15, 1971, pp. 785-790.
10. A. Bauer, P. Cybulskis, and R. Petty, "Helium- and sodium-bonded mixed nitride fuel performance," in: Proceedings on Fast Breeder Fuel Performance, Monterey, USA, March 5-8, 1979, pp. 827-832.
11. A. Bauer, P. Cybulskis, and J. Green, "Mixed-nitride fuel performance in EBR II," in: Proceedings of a Symposium on Advanced LMFBR Fuels, Tucson, USA, ERDA-4455, October 10-13, 1977, p. 299.
12. H. Blank, K. Richter, and M. Coquerelle, "Dense fuels in Europe," J. Nucl. Mater., 166, No. 1-2, 95-104 (1989).
13. R. Mattheus, et al., "Fabrication and testing of uranium nitride fuel for space power reactors," J. Nucl. Mater., 151, No. 3, 217-222 (1988).
14. C. Ganguly, P. Hegde, and A. Sengupta, "Preparation, characterization, and out-of-pile property evaluation of (U, Pu)N fuel pellets," J. Nucl. Mater., 178, 234-241 (1991).
15. M. Coquerelle and C. Walker, "Fission gas release and microscopic swelling in high rated advanced fuels," J. Nucl. Technol., 48, 43-50 (1979).
16. V. A. Makhova, "Fast reactors abroad. Promising forms of fuel for LMFBR reactors," Obz. Inform., No. 5, TSNIIatominform, Moscow (1982).
17. S. Weaver, Report ORNL-4461 (1969).
18. K. Bagley et al., "Fuel element behavior under irradiation in DFR," in: Proceedings of Symposium on Fuel and Fuel Elements for Fast Reactors, Brussels, July 2-6, 1973, Vol. 1 (1974), pp. 97-100.
19. Y. Arai, Y. Suzuki, and A. Handa, "Experimental research on nitride fuel cycle in JAERI," in: Proceedings of International Conference on Future Nuclear Systems, Global'99, ANS (1999).
20. Y. Arai, Y. Suzuki, T. Iwai, et al., "Fabrication of uranium-plutonium mixed nitride fuel pins for irradiation tests in JMTR," J. Nucl. Sci. Technol.,30(8), 824-830 (1993).
21. H. Bernard, "Advanced fuel fabrication," J. Nucl. Mater., 166, 105-111 (1989).
22. A. V. Petrov, G. B. Usynin, and S. G. Usynina, "Combined pyroprocessing-based fuel cycle for fast and VVÉR reactors," At. Énerg., 85, No. 6, 451-457 (1998).
23. C. Till and Y. Chang, "Progress and status of integral fast reactor (IFR). Fuel cycle development," in: Proceedings of the American Power Conference 55-11, Illinois Institute of Technology (1993), pp. 1070-1074.
24. J. Laidler, J. Battles, and W. Miller, "Development of IFR pyroprocessing technology," in: Conference Global'93. Future on Nuclear Systems-Emerging Fuel Cycles and Waste Disposal Options, September 12-17, 1993.
25. V. A. Tsykanov, O. V. Skiba, and G. I. Gadzhiev, "Factors and preliminary assessment of the cost-effectiveness of central nuclear heat and power generation based on nuclear power plants with fast reactors," At. Énerg., 67, No. 3, 163-166 (1989).
26. Y. Suzuki, "Research and development of nitride fuel cycle for TRU burning," in: Actinide and Fission Product Partitioning and Transmutation. Proeedings of 4th International Exchange Meeting, Mito City, Japana, September 13-15, 1996, OECD NEA (1997), pp. 178-188.
27. L. M. Zabud'ko, L. A. Kochetkov, B. D. Rogozkin, et al., "Prospects for use of nitride fuel in fast power reactors," in: Nuclear Fuel for Mankind. Scientific and Technical Conference of the Nuclear Society of Russia, Élektrostal', October 5-8, 1998.
28. A. G. Vakhtin, V. D. Dmitriev, S. N. Ermolaev, et al., "Experience in operating fuel elements in a nitride core of a BR-10 reactor," Report at a Soviet-French Seminar, Obninsk (1992).
29. V. D. Dmitriev, L. I. Moseev, A. G. Vahtin, et al., "Capacity for work mononitride fuel in the reactor BR-10 with burning until 8.2% h.a.," in: 3rd Conference on Reactor Materials, Dimitrovgrad, Russia (1993) [sic].
30. S. Hayes, J. Thomas, and K. Reddicord, "Material, property correlations for uranium mononitride," J. Nucl. Mater., 71, 262-318 (1990).
31. B. D. Rogozkin, N. M. Stepennova, and Yu. E. Fedorov, "Mononitride mied fuel for fast reactors," in: Technical Communications on Unconventional Options for Pu Disposition, November 7-11, 1994, Obninsk, Russia, IAEA-TECDOC-840 (1995), pp. 229-236.
32. S. N. Tarasov, A. N. Evstyukhin, V. I. Knyazev, et al., "Creep of uranium carbonitrides," Vopr. At. Nauk. Tekh. Ser. At. Materialov., No. 1(12), 9-12 (1983).
33. J. Routbort and R. Singh, "Elastic, diffusional, and mechanical properties of carbide and nitride nuclear fuels. A review," J. Nucl. Mater., 58, 78-114 (1975).
34. Y. Suzuki and Y. Arai, "Thermophysical and thermodynamic properties of actinide mononitrides and their solid solutions," J. Alloys and Compounds, 271-273, 577-582 (1998).
35. H. Kleykamp, "Selection of materials as diluents for burning of plutnoium fuels in nuclear reactors," J. Nucl. Mater., 275, 1-11 (1999).
36. D. Brucklacher and W. Dienst, "Creep behavior of ceramic nuclear fuels under irradiation," J. Nucl. Mater., 42, No. 3, 285-291 (1972).
37. I. S. Golovnin, B. D. Rogozkin, A. K. Serov, et al., "Radiation studies of carbide-nitride uranium and mixed uranium-plutonium nitride fuel," in: Proceedings of an International Conference on Radiation Materials Science, Alushta (1990), pp. 47-55.
38. P. Zeisser, G. Maraniello, and C. Merlin, "In-pile measurement of fission enhanced creep and swelling of uranium nitride," J. Nucl. Mater., 65, 48-53 (1977).
39. W. Dienst, "Irradiation induced creep of ceramic nuclear fuels under neutron irradiation," J. Nucl. Mater., 42, 285-288 (1972).
40. Yu. G. Degal'tsev, N. N. Ponomarev-Stepnoi, and V. F. Kuznetsov, Behavior of High-Temperature Fuel under Irradiation, Énergoatomizdat, Moscow (1987).
41. Y. Suzuki, Y. Arai, and T. Iwai, "Performance of U-Pu mixed nitride fuel under irradiation," in: Conference of Future Nuclear Systems, October 5-10, 1992, Japan, pp. 523-530.
42. T. Iwai, K. Nakajimi, H. Kikuchi, et al., "Post-irradiation examinations of uranium-plutonium mixed nitride fuel irradiated in JMTR," in: Report JAERI-Research 2000-010, January 26, 2000.
43. B. Makenas, J. Hales, and A. Ward, "Fuels irradiation testing for the SP-100 program," in: Proceedings of the 8th Symposium on Space Nuclear Power Systems, Albuquerque, New Mexico, USA, January 6-10, Part II (1991), pp. 886-890.
44. C. Prunier, P. Bardelle, and J. Pauges, "European collaboration on mixed nitride fuel," in: Proceedings of International Conference on Fast Reactors and Related Fuel Cycles, Kyoto, Japan, October 28-November 1, 1991, Vol. II, pp. 1.5.9-1.5.12.
45. Y. Arai, Y. Suzuki, T. Iwai, et al., "Research and development of nitride fuel and its fuel cycle for FR at JAERI," in: Proceedings of Advisory Group Meeting, IAEA, Vienna, TECDOC-850 (1994).
46. S. Ross and M. El-Genk, "Uranium nitride fuel swelling correlation, thermal conductivity correlation for uranium nitride fuel between 10 and 1923 K," J. Nucl. Mater., 171, 67-75 (1990).
47. C. Crando, M. Montgomery, and A. Strasser, "UN swelling and fission gas release on fast reactors fuel element," in: Proceedings of ANS Conference on Fast Reactor Fuel Element Technology (1971), pp. 771-784.
48. T. Washburn, K. Thomas, and S. Weaver, "Examination of UN-fuel pins irradiated at 1400°C," J. Trans. Amer. Nucl. Soc., 13, 101-102 (1970).
49. M. Colin, "Sodium bonding pin concept for advanced fuel," J. Nucl. Mater., 116, 35-38 (1983).
50. Yu. A. Zakharko, A. A. Proshkin, and B. D. Rogozkin, "Concept of fuel elements for power reactors with sodium fill," Preprint IAÉ-5773/1 (1994).
51. B. D. Rogozkin, N. M. Stepennova, O. A. Alekseev, et al., "Preliminary experimental substantiation of the construction of a fuel element with mononitride fuel and lead sublayer for the BREST reactor," in: International Seminar on the Use of Heavy Liquid Metal Coolants, Obninsk, October (1998).
52. I. I. Raevskii, Development of Nitride Fuel for Space-Based Reactors Abroad. Review, TSNIIatominform, Moscow (1991).
53. K. Blank, "Basic aspects of swelling in dense liquid metal fast breeder reactor fuels," J. Less-Common Metals, 121, 583-588 (1985).
54. A. Bauer and V. Storhok, "Irradiation studies of (U, Pu)N," in: Proc. Plutonium and Other Actinides, Santa Fe, USA October 5-9, 1970, pp. 532-538.
55. Yu. I. Likhachev and V. Ya. Pupko, Strength of Fuel Elements for Nuclear Reactors, Atomizdat, Moscow (1975).
56. Yu. A. Zakharko and A. A. Proshkin, "Analytical method for calculating stresses and deformations in a fuel element," Preprint IAÉ-4945/4 (1988).
57. Yu. A. Zakharko, A. A. Proshkin, and A. A. Shestopalov, "Description of the TEGAS method and computer program for calculating the behavior of power-reactor fuel elements," Preprint IAÉ-4945/4 (1989).
58. E. Storms, "An equation which describes fission gas release from UN reactor fuel," J. Nucl. Mater., 158, 119-129 (1988).
59. Y. Arai, Y. Suzuki, and Y. Okamoto, "NpN thermal conductivity of neptunium mononitride from 740 to 1600 K," J. Nucl. Mater., 211, No. 3, 248-252 (1994).
60. R. B. Kotel'nikov, S. N. Bashlykov, A. I. Kashtanov, and T. S. Men'shikova, High-Temperature Nuclear Fuel, Atomizdat, Moscow (1978).
61. K. Richter and K. Blank, J. Trans. Amer. Nucl. Soc. (1990), p. 319.
62. B. D. Rogozkin, O. N. Dubrovin, N. M. Stepennova, et al., "Mononitride mixed U-Pu fuel and its electrochemical recovery in fused salts," in: Reports at the International Seminar on Fast Reactors and Inherently Safe Fuel Cycle for Large-Scale Power Production. Fuel Balance, Economics, Safety, Wastes, Nonproliferation, Minatom Rossii, Moscow, May 29 - June 1, 2000.
63. G. Toshinski, "Pb-Bi cooled fast reactor concept (SVBR-75/100) with a focus on proliferation resistance and other requirements for innovative technologies. New generation of future systems for nuclear energy, emphasizing proliferation resistance issues," in: CEA-IBRAE-Kurchatov Workshop, March 5-6, 2002, Saclay Bat, 125, Room Venus.