Thermo-mechanical analysis of a cracked fuel pellet and cladding using the finite element method = 유한요소법을 이용한 균열된 핵연료 페레트와 피복관의 열-역학적 분석

Cited 0 time in webofscience Cited 0 time in scopus
  • Hit : 301
  • Download : 0
This paper describes a three-dimensional finite element method programme, named TOMAC, for the analysis of thermo-mechanical behavior of the fuel rod system under power increase. In the development of the code, the isoparametric finite element formulation is adopted, and the Galerkins`` technique is used in the derivation of the thermal element equation, and the principle of virtual displacements is used in the derivation of the displacement element equation. The pellet-cladding interaction mechanism is exactly treated using the nodal equilibrium equations and continuity conditions with various frictional conditions. The combined initial and tangential stiffness approach is used to solve non-linear system efficiently. The transient temperature distribution is solved by a step-by-step time incremental procedure and introduced into the elasto-plastic analysis as a thermal load and stresses and deformation are calculated. In order to validate the code, TOMAC, the time dependent temperature distribution of a solid cylinder with heat source and the elasto-plastic stress distribution of a hollow cylinder with internal pressure and thermal stress distribution of a hollow cylinder with a temperature gradient are calculated and compared with the analytical solutions. Comparisons of the results predicted by TOMAC to the analytical solutions show quite good agreements. The finite element geometrical model is confined to a half-pellet-height region. And the temperature distribution, deformation, and the thermo-elasto-plastic stress distribution of a cracked and non-cracked fuel rod system, which are calculated by TOMAC, show correct qualitative trends. And the effects of the dish and chamfer are examined.
No, Hee-Cheonresearcher노희천researcher
한국과학기술원 : 핵공학과,
Issue Date
65994/325007 / 000851433

학위논문(석사) - 한국과학기술원 : 핵공학과, 1987.2, [ vii, 76 p. ]

Appears in Collection
Files in This Item
There are no files associated with this item.


  • mendeley


rss_1.0 rss_2.0 atom_1.0