Recommendations for calculating the characteristics of thermal creep of mixed uranium-plutonium oxide fuel when analyzing fuel-element serviceability

Atomic Energy

Volumn 108, Issue 1, 2010, Pages 15-20

  Malygin, V B ^a   Naboichenko, K V ^a   Shapovalov, A S ^a   Bibilashvili, Yu K ^b  

^a NATIONAL RESEARCH NUCLEAR UNIVERSITY MEPHI   (Russian Federation)

^b Bochvar All Russia Research Institute for Inorganic Materials (VNIINM)   (Russian Federation)

Author keywords

[No Author keywords available]

Indexed keywords

COEFFICIENT OF DIFFUSION; CONTROLLED MOTIONS; CREEP RATES; DEFORMATION PROCESS; DISPLACEMENT MECHANISMS; EFFECT OF TEMPERATURE; EMPIRICAL RELATIONS; EXPERIMENTAL DATA; FUEL DENSITY; FUEL ELEMENTS; GRAIN SIZE; IONIC CRYSTALS; MIXED URANIUM-PLUTONIUM OXIDES; PHYSICAL MODEL; SUB-LATTICES; THERMAL CREEP;

DIFFUSION; DISLOCATIONS (CRYSTALS); FUELS; NUCLEAR FUEL ELEMENTS; OXYGEN; PLUTONIUM; PLUTONIUM COMPOUNDS; POINT DEFECTS; URANIUM;

CREEP;

EID: 77952121787     PISSN: 10634258     EISSN: None     Source Type: Journal    
DOI: 10.1007/s10512-010-9250-y     Document Type: Article

References (12)

1. VB Malygin KV Naboichenko AS Shapovalov YuK Bibilashvili 2009 Recommendations for calculating the characteristics of thermal creep of uranium dioxide when analyzing the serviceability of fuel elements At. Énerg. 107 6 317 320
2. L. Girifalco, Statistical Mechanics of Solids [Russian translation], Mir, Moscow (1975).
3. S. E. Lemekhov, "Diffusion-track model of finish sintering of uranium dioxide under reactor conditions," Preprint IAE-4553/11 (1988).
4. J Routbort 1973 Creep of mixed oxide fuel pellets at high stress J. Amer. Ceram. Soc. 56 6 330 338 10.1111/j.1151-2916.1973.tb12507.x
5. J Routbort 1972 Compressive creep of mixed oxide fuel pellets J. Nucl. Mater. 44 3 247 253 10.1016/0022-3115(72)90036-0 1972JNuM...44..247R
6. 2 nuclear fuel pellets," in: Proc. Int. onf. IAEA Thermodynamics of Nuclear Materials (1974), Vol. 1, pp. 435-446.
7. 2 compounds," in: Proc. 4th Int. Conf. Plutonium 1970 and Other Actinides, Vol. 17, pp. 478-487.
8. 2," ibid., pp. 488-496.
9. 2," ibid., pp. 497-509.
10. Matpro - a Library of Materials Properties for Light Water Reactor Accident Analysis, US Nuclear Regulatory Commission, Washington (1995).
11. 2 J. Nucl. Mater. 42 101 104 10.1016/0022-3115(72)90013-X 1972JNuM...42..101P
12. L. Caillot, C. Ninon, and V. Basini, "Out of pile and in-pile viscoplastic behavior of mixed oxide fuels," in: Proc. Int. Seminar on Pellet - Clad Interaction in Water Reactor Fuels, Cadarache, France, March 9-11, 2004, pp. 205-212.