3D fuel cracking modelling in pellet cladding mechanical interaction

Engineering Fracture Mechanics

Volumn 75, Issue 11, 2008, Pages 3581-3598

  Michel, B ^a   Sercombe, J ^a   Thouvenin, G ^a   Chatelet, R ^a  

^a IRFM   (France)

Author keywords

Failure behaviour; Pellet cladding interaction (PCI); PWR

Indexed keywords

CONSTITUTIVE MODELS; CRACK INITIATION; CREEP; FAILURE ANALYSIS; FINITE ELEMENT METHOD; MATHEMATICAL MODELS; NUCLEAR FUEL PELLETS; STRESS RELAXATION; THREE DIMENSIONAL; VISCOPLASTICITY;

FAILURE BEHAVIOR; PELLET-CLADDING INTERACTION; PRESSURE WATER REACTOR;

NUCLEAR FUEL CLADDING;

CONSTITUTIVE MODELS; CRACK INITIATION; CREEP; FAILURE ANALYSIS; FINITE ELEMENT METHOD; MATHEMATICAL MODELS; NUCLEAR FUEL CLADDING; NUCLEAR FUEL PELLETS; STRESS RELAXATION; THREE DIMENSIONAL; VISCOPLASTICITY;

EID: 41749113065     PISSN: 00137944     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.engfracmech.2006.12.014     Document Type: Article

References (19)

1. 2 and MOX fuel with METEOR/TRANSURANUS version 1.5, ANS International Topical Meeting on Light Water Reactor Fuel Performances, Portland, 1997.
2. Brochard J, Bentejac F, Hourdequin N. Non-linear finite element studies of the pellet cladding mechanical interface in PWR fuel. In Transactions of the 14th SMIRT, Lyon, France, 1997. TOUTATIS an application of the CAST3M finite element code for PCI three dimensional modelling".
3. Lassmann K., and Blank H. Modelling of fuel rod behaviour and recent advances of the TRANSURANUS Code. Nucl Eng Des 106 (1988) 291-313
4. Garcia P., Struzik C., Agard M., and Louche V. Mono-dimensional mechanical modelling of fuel rods under normal and off-normal operating conditions. Nucl Eng Des 216 1-3 (2002) 183-201
5. Bentejac F. TOUTATIS an application of the CAST3M finite element code for PCI three dimensional modelling, International seminar on PCI, Aix en Provence, March 2004.
6. Thouvenin G, Ricaud JM, Michel B. ALCYONE: the PLEIADES fuel performance code dedicated to multidimensional PWR studies. In International Meeting on LWR Fuel Performance, Spain: 2006.
7. Plancq D. PLEIADES: a unified environment for multi-dimensional fuel performance modelling, International Meeting on LWR Fuel Performance, Florida: 2004.
8. 2 Fuel: review and recommendations. J Nucl Mater 232 (1996) 166-180
9. Contesti E. Description of creep-plasticity interaction with non-unified constitutive equation. Nucl Eng Des 116 3 (1989) 265-280 Sept. (II)
10. Soniak A., L'hullier N., Mardon J.P., Rebeyrolle V., Bouffioux P., and Bernaudat C. Irradiation creep behavior of Zr-base alloys. In: Moan G.D., and Rudling P. (Eds). Zirconium in the nuclear industry: thirteenth international symposium. ASTM STP 1423 (2002), ASTM International, West Conshohocken, PA 837-862
11. Lassmann K., and Hohlefeld F. The revised URGAP model to describe the gap conductance between fuel and cladding. Nucl Eng Des 103 (1987) 215-221
12. Nonon C. Differential PCI behaviour of PWR fuel rods under transient conditions. Int Meeting on LWR Fuel Performance, Florida, 2004.
13. Monerie Y., and Gatt J.M. Overall viscoplastic behaviour of non irradiated porous nuclear ceramics. Mech Mater 38 7 (2006) 608-619
14. Besson J. Application de l'approche locale de la rupture à la simulation de la fissuration des structures: problèmes numériques liés à l'existence d'une longueur interne, Colloque National Mecamat, 2004, p. 206-14.
15. Helfer T. Étude de l'impact de la fissuration des combustibles nucléaires oxyde sur le comportement normal et incidentel des crayons combustibles, École Centrale de Lyon, Soutenue le 17-03-06.
16. Dahlblom O., and Ottosen N. Smeared crack analysis using generalized fictious crack model. J Eng Mech 116 (1990) 55-76
17. Hellen T.K. On the method of virtual crack extension. Int J Numer Meth Eng 9 (1975) 187-207
18. Millard A. Contribution à la modélisation à plusieurs échelles des matériaux et des structures, Mémoire d'habilitation à diriger des recherches, Ecole doctorale MEGA, Lyon, 1996.
19. Michel B. PCMI assessment using 3D modelling, SMIRT18, Beijing, 2005.