A review of TRISO fuel performance models

Abstract Several advanced reactor designs incorporate tristructural isotropic (TRISO) fuel particles to achieve high coolant temperature and high fuel burnup levels and thus require reliable and robust fuel performance models (FPMs) to evaluate reactor performance. This manuscript provides a detailed and concise review of the numerous published TRISO FPMs. The article begins with a brief review of TRISO fuel particles, before describing the important fuel behavior and failure mechanisms of TRISO fuel. Suggested material property correlations for use in TRISO fuel performance modeling are summarized with an emphasis on the limits of validity for those correlations and notes regarding their use and origin. A review of the major historical and current TRISO FPMs assesses each model’s capabilities and origin and provides a systematic comparison of the codes to document similarities and differences in their features. Finally, areas of improvement and unsolved problems are discussed that may limit the accuracy of TRISO fuel performance modeling.

[1]  R. Bullock.  Fission-product release during postirradiation annealing of several types of coated fuel particles , 1984 .

[2]  Donald R. Olander,et al.  Fundamental Aspects of Nuclear Reactor Fuel Elements , 1976 .

[3]  Kazuhiro Sawa,et al.  Research and development on HTGR fuel in the HTTR project , 2004 .

[4]  Lei Shi,et al.  Benchmark Calculation for the Steady-State Temperature Distribution of the HTR-10 under Full-Power Operation , 2009 .

[5]  David G. Martin,et al.  Considerations pertaining to the achievement of high burn-ups in HTR fuel , 2002 .

[6]  T. Liang,et al.  A review of TRISO-coated particle nuclear fuel performance models , 2006 .

[7]  Masato Kato,et al.  Thermal conductivities of hypostoichiometric (U, Pu, Am)O2−x oxide , 2008 .

[8]  D. Petti,et al.  Updated solution for stresses and displacements in TRISO-coated fuel particles , 2008 .

[9]  K. Ikawa,et al.  Release of metal fission products from UO2 kernel of coated fuel particle , 1985 .

[10]  D. J. Varacalle,et al.  Statistical approach and benchmarking for modeling of multi-dimensional behavior in TRISO-coated fuel particles , 2003 .

[11]  Kazuo Minato,et al.  Fission product release from ZrC-coated fuel particles during post-irradiation heating at 1800 and 2000°C , 1997 .

[12]  D. Petti,et al.  An evaluation of the effects of SiC layer thinning on failure of TRISO-coated fuel particles , 2006 .

[13]  B. Boer,et al.  Stress Analysis of Coated Particle Fuel in Graphite of High-Temperature Reactors , 2008 .

[14]  David A. Petti,et al.  Project Deep-Burn: Development of Transuranic Fuel for High-Temperature Helium-Cooled Reactors , 2008 .

[15]  Gregory K. Miller,et al.  Current Capabilities of the Fuel Performance Modeling Code PARFUME , 2004 .

[16]  B. Boer,et al.  Development of a stress analysis code for TRISO particles in HTRs , 2008 .

[17]  H. Nabielek,et al.  Development of advanced HTR fuel elements , 1990 .

[18]  Kazuo Minato,et al.  Fission product palladium-silicon carbide interaction in htgr fuel particles , 1990 .

[19]  D. Petti,et al.  Consideration of the effects of partial debonding of the IPyC and particle asphericity on TRISO-coated fuel behavior , 2004 .

[20]  Kazuhiro Sawa,et al.  Irradiation Experiment on ZrC-Coated Fuel Particles for High-Temperature Gas-Cooled Reactors , 2000 .

[21]  T. Ogawa,et al.  Release behavior of metallic fission products from HTGR fuel particles at 1600 to 1900°C , 1993 .

[22]  Gregory K. Miller,et al.  Key differences in the fabrication, irradiation and high temperature accident testing of US and German TRISO-coated particle fuel, and their implications on fuel performance , 2003 .

[23]  Kazuo Minato,et al.  Retention of fission product caesium in ZrC-coated fuel particles for high-temperature gas-cooled reactors , 2000 .

[24]  J. Schöning,et al.  Construction and operating experience with the 300-MW THTR nuclear power plant , 1990 .

[25]  B. Boer,et al.  Optimized Core Design and Fuel Management of a Pebble-Bed Type Nuclear Reactor , 2009 .

[26]  Kaifen Zuo,et al.  Overview of the 10 MW high temperature gas cooled reactor—test module project , 2002 .

[27]  G. Miller.  STRESSES IN A SPHERICAL PRESSURE VESSEL UNDERGOING CREEP AND DIMENSIONAL CHANGES , 1995 .

[28]  Shusaku Shiozawa,et al.  Research and Development of HTTR Coated Particle Fuel , 1991 .

[29]  Y. Katoh,et al.  Handbook of SiC properties for fuel performance modeling , 2007 .

[30]  K. Minato,et al.  Deterioration of ZrC-coated fuel particle caused by failure of pyrolytic carbon layer , 1998 .

[31]  Shusaku Shiozawa,et al.  Development of a Coated Fuel Particle Failure Model under High Burnup Irradiation , 1996 .

[32]  Gregory K. Miller,et al.  Consideration of the effects on fuel particle behavior from shrinkage cracks in the inner pyrocarbon layer , 2001 .

[33]  Gregory K. Miller,et al.  The challenges associated with high burnup, high temperature and accelerated irradiation for TRISO-coated particle fuel , 2007 .