Spherical Shell
Material presented here is a subset of information in Hales et al. (2021) and Hales et al. (2013). See the JNM papers for more information.
CRP-6 Assessment Cases
As part of an International Atomic Energy Agency (IAEA) Coordinated Research Program (CRP-6) on High Temperature Gas Reactor (HTGR) reactor fuel technology, a set of benchmarking activities were developed to compare fuel performance codes under normal operation and operational transients (IAEA, 2012). Sixteen fuel performance benchmark cases were identified. The first three of these involve stress in spherical shells.
Fuel Performance Results
Cases 1 to 3 were limited to single and double coating layers for TRISO fuel particles and tested simple elastic thermomechanical behavior against analytical solutions.
The tangential stress as a function of radial coordinate, , is given as (Roark and Young, 1975): where and are the inner and outer pressures and and are the inner and outer radii.
In all three cases, = 25E6 and = 1E5.
A comparison of the analytical and Bison numerical solutions for the maximum tangential stress, which occurs at the inner surface of the various layers, is shown in Table 1.
Table 1: Comparison of the Bison computed maximum tangential stress (MPa) to the analytical solution for Cases 1 to 3.
| Case | Radii (m) | Layer | Analytical (MPa) | Bison (MPa) | Error (%) |
|---|---|---|---|---|---|
| 1 | 3.5E-4/3.85E-4 | SiC | 125.190 | 125.13 | 0.048 |
| 2 | 3.5E-4/4.4E-4 | IPyC | 50.200 | 50.176 | 0.048 |
| 3 | 3.5E-4/3.9E-4/4.25E-4 | IPyC/SiC | 8.8/104.4 | 8.7/104.5 | 1.14/0.10 |
References
- J.D. Hales, R.L. Williamson, S.R. Novascone, D.M. Perez, B.W. Spencer, and G. Pastore.
Multidimensional multiphysics simulation of TRISO particle fuel.
Journal of Nuclear Materials, 443(1):531–543, 2013.
doi:10.1016/j.jnucmat.2013.07.070.[BibTeX]
- Jason D. Hales, Wen Jiang, Aysenur Toptan, and Kyle A. Gamble.
Modeling fission product diffusion in TRISO fuel particles with BISON.
Journal of Nuclear Materials, 548:152840, 2021.
doi:10.1016/j.jnucmat.2021.152840.[BibTeX]
- IAEA.
Advances in high temperature gas cooled reactor fuel technology.
Technical Report IAEA-TECDOC-1674, International Atomic Energy Agency, 2012.[BibTeX]
- R. J. Roark and W. C. Young.
Formulas for Stress and Strain.
McGraw-Hill Inc., United States, 1975.[BibTeX]