Gas Tightness Evaluation of Structural Concrete Applied to Nuclear Containment Vessels

The presence of high-temperature air-steam mixes and their transport is the most important factor controlling the security reliability of nuclear containment vessels during a loss of coolant accident. Total accumulated amount of radioactive substances and their hazards cannot be ignored, although the release process through non-cracked structural concrete is very slow. Through established models of flow through structural concrete of containment vessels, permeability coefficients and leakage rate under steady and accident state are discussed in this paper. Comparison results of tightness show that properties of structural concrete applied to containment vessels should be strictly controlled and regulated.

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