Simulation of Pellet-Cladding Interaction with the PLEIADES Fuel Performance Software Environment

REFERENCES

• D. Plancq et al., “PLEIADES: A Unified Environment for Multi-Dimensional Fuel Performance Modelling,” Proc. Int. Mtg. Light Water Reactor Fuel Performance, Orlando, Florida, September 19–22, 2004, American Nuclear Society (2004).
   Google Scholar
• C. Struzik, M. Moyne, and J.-P. Piron, “High Burnup Modelling of UO2 and MOX Fuel with METEOR/TRANSURANUS Version 1.5,” Proc. Int. Mtg. Light Water Reactor Fuel Performance, Portland, Oregon, March 2–6, 1997, p. 126, American Nuclear Society (1997).
   Google Scholar
• I. M. Palmer, K. W. Hesketh, and P. A. Jackson, “A Model for Predicting the Radial Power Profile in a Fuel Pin,” Proc. Specialists’ Mtg. Water Reactor Fuel Element Performance Computer Modelling, Preston, United Kingdom, International Atomic Energy Agency (1992).
   Google Scholar
• P. Reuss, “Base de neutronique—Migration des neutrons,” BN 3014, Technique de l’IngÃnieur (2005).
   Google Scholar
• F. Lemoine, D. Bernard, and E. Federici, “Validation Assessment of Neutron Calculations for Radial and Azi-muthal Distributions of Actinides and Fission Products in PWR Rods,” presented at 2011 Water Reactor Fuel Performance Mtg., Chengdu, China, September 11–14, 2011.
   Google Scholar
• Y. Monerie and J. M. Gatt, “Overall Viscoplastic Behaviour Of Non Irradiated Porous Nuclear Ceramics,” Mech. Mater., 38, 608 (2006).
   Google Scholar
• B. Michel et al., “3D Fuel Cracking Modelling in Pellet Cladding Mechanical Interaction,” Eng. Fracture Mech., 75, 3581 (2008).
   Google Scholar
• A. Soniak et al., “Irradiation Creep Behavior of Zr-Base Alloys,” Zirconium in the Nuclear Industry: 13th International Symposium, ASTM STP 1423, p. 837, G. D. Moan and P. Rudling, Eds., ASTM International, West Conshohocken, Pennsylvania (2002).
   Google Scholar
• G. Roberts, “The Concentration of Stress in Cladding Produced by the Expansion of Cracked Fuel Pellets,” Nucl. Eng. Des., 47, 257 (1978).
   Google Scholar
• J. Brochard et al., “Modelling of Pellet Cladding Interaction in PWR Fuel,” Trans. SMIRT16 (2001).
   Google Scholar
• E. Smith, “The Fuel-Cladding Interfacial Friction Coefficient in Water-Cooled Reactor Fuel Rods,” Trans. SMIRT 5 (1979).
   Google Scholar
• J. C. Wood, B. A. Surette and I. Aitchison, “Pellet Cladding Interaction—Evaluation of Lubrification by Graphite,” J. Nucl. Mater., 88, 81 (1980).
   Web of Science ®Google Scholar
• A. Boulore, “étude et modélisation de la densification en pile des oxydes nucléaires UO2 et MOX,” Thesis, Ecole Nationale Supérieure des Mines de Saint-Étienne, Institut National Polytechnique de Grenoble (2001).
   Google Scholar
• Ph. GARCIA, C. Struzik, and M. Agard, “The Effect of Fission Gas Swelling on Cladding Strains During Power Ramp Tests,” Proc. Conf. Fuel Chemistry and Pellet Cladding Interaction Related to High Burn-Up Fuel, Nyköping, Sweden, September 7–10, 1998, IAEA TECDOC 1179, International Atomic Energy Agency (1998).
   Google Scholar
• L. Noirot, “MARGARET: An Advanced Mechanistic Model of Fission Gas Behaviour in Nuclear Fuel,” Nucl. Eng. Des., 241, 6, 2099 (2011).
   Google Scholar
• B. Michel, “PCMI Assessment Using 3D Modelling,” Trans. SMIRT 18 (2005).
   Google Scholar
• J. Sercombe, et al., “1D and 3D Analyses of the Zy2 SCIP BWR Ramp Tests with the Fuel Codes METEOR and ALCYONE,” Nucl. Eng. Technol., 41, 2 (Mar. 2009).
   Google Scholar
• P. Garcia et al., “Mono-Dimensional Mechanical Modelling of Fuel Rods Under Normal and Off-Normal Operating Conditions,” Nucl. Eng. Des., 216, 1–3, 183 (July 2002).
   Google Scholar
• J. Sercombe et al., “Multi-Dimensional Modeling of PCMI During Base Irradiation and Ramp Testing with ALCYONE V1.1,” Proc. Top Fuel 2009, Paris, France, September 2009.
   Google Scholar
• L. E. Herranz et al., “Assessment of Fuel Rod Performance Codes Under Ramp Scenarios Investigated Within the SCIP Project,” Nucl. Eng. Des., 241, 3, 815 (Mar. 2011).
   Google Scholar
• J. Sercombe et al., “1D and 3D Modeling of PCMI During a RIA with ALCYONE V1.1,” Proc. Top Fuel 2010, Orlando, Florida, September 2010.
   Google Scholar
• B. Michel, J. Sercombe, and G. Thouvenin, “A New Phenomenological Criterion for Pellet Cladding Interaction Rupture,” Nucl. Eng. Des., 238, 1612 (2008).
   Google Scholar
• L. Barbie et al., “AMR Methods in Solids Mechanics for Pellet-Cladding Interaction Modeling,” presented at European Community in Computational Methods in Applied Sciences Int. Conf. Adaptive Modeling and Simulation (ADMOS 2011), Paris, France, June 6–8, 2011.
   Google Scholar