TY - JOUR
T1 - Thermally induced radial cracking in fuel element pellets
AU - Sumi, Y.
AU - Keer, L. M.
AU - Nemat-Nasser, S.
N1 - Funding Information:
This work was supportedb y National Science Foundation Grant No. ENG 77-22155t o North-westernU niversityT. he authorsa re gratefutl o Pro-fessorM .C. Biilone for helpfuld iscussioncso ncerning the design,o peratingc onditions,a nd propertieso f nuclearfu el rods.
PY - 1981/1
Y1 - 1981/1
N2 - An investigation is made of the fracture properties of cylindrical nuclear fuel pellets. Using concepts from linear elastic fracture analysis and considering the stability of patterns of interacting cracks, the propagation of radial surface cracks into a cylindrical fuel column under the influence of thermal loading is studied. It is found that irrespective of the number of symmetrically placed cracks, only two cracks on opposite sides will tend to propagate until they coalesce. The nature of the crack growth until failure deduced from concepts of stability is discussed in detail. Numerical results using data for a typical advanced core fuel rod with mixed-carbide [UC + PuC] fuel, are given.
AB - An investigation is made of the fracture properties of cylindrical nuclear fuel pellets. Using concepts from linear elastic fracture analysis and considering the stability of patterns of interacting cracks, the propagation of radial surface cracks into a cylindrical fuel column under the influence of thermal loading is studied. It is found that irrespective of the number of symmetrically placed cracks, only two cracks on opposite sides will tend to propagate until they coalesce. The nature of the crack growth until failure deduced from concepts of stability is discussed in detail. Numerical results using data for a typical advanced core fuel rod with mixed-carbide [UC + PuC] fuel, are given.
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U2 - 10.1016/0022-3115(81)90228-2
DO - 10.1016/0022-3115(81)90228-2
M3 - Article
AN - SCOPUS:0019478178
SN - 0022-3115
VL - 96
SP - 147
EP - 159
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
IS - 1-2
ER -