Fracture probability integral applied to reactor vessel life estimate

The conventional method of fracture probability calculations such as that a dopted by the NRC-sponsored PRAISE CODE and the FAVOR CODE developed in thi s laboratory are both based on Monte Carlo simulation. Heavy computations a re required. A new method of fracture probability calculation is developed by direct probability integration. The preliminary version of the developme nt was published in an earlier paper. More detailed development of the meth od is presented here. The present approach offers simple and expedient meth od to obtain numerical values of fracture probability. This method can be a pplied to problems as general as the method of Monte Carlo simulation. This approach also provides a clear physical picture on the meaning of the prob ability of fracture. Parametric studies are made in this paper to show the variation of the numerical values of the probabilities of fracture as a res ult of the change of the standard deviation of either fracture toughness or the radiation-induced temperature shift. Also, it is shown numerically tha t a limiting probability can be obtained if the standard deviation of the f racture toughness approaches zero that implies a deterministic fracture tou ghness. It confirms the theoretical proof shown in Eq. (11). The limiting p robability is the simplistic probability of crack count used by this author where both toughness and temperature shift are assumed to be deterministic values. The general probability of fracture developed here is simply a gen eralization of the crack count, except the crack count is selected with the appropriate fracture toughness in the toughness distribution. The toughnes s for the problem considered here is then multiplied by the appropriate tem perature shift in the distribution function of the temperature shift. Altho ugh the present development is based on linear fracture mechanics assumptio n and applied to the radiated reactor vessel steel, there is no difficulty in viewing the present development as a general formulation that is capable of handling as many random variables as required by the fracture model. Th e multiplicity of the integration corresponds to the number of random varia bles. The probability integral is applied in this paper to calculate the pr obability of fracture for the high flux isotope reactor (HFIR) vessel that has been weakened due to the radiation embrittlement. The random variables used here are the crack length, the fracture toughness, and the radiation-i nduced temperature shift that is needed in the Parametric representation of the radiated vessel steel.