Investigation of the compatibility of the Brinkman-Seeger damage model with results of steel irradiation

The knowledge of the mathematical formulation between neutron flow and spectrum on the one hand, and damages in reactor structure materials (notably vessel steel and graphite) on the other hand, allows the comparison of irradiation experiments performed in different reactors and the perspective of practical applications in problems of material strength. After having outlined that irradiation of steels by neutrons results in an increase of the ductile to brittle transition temperature, and in a decrease of the maximum energy of ductile failure, the author reports an interpretation of irradiations of American steels by using response functions and dose functions for the creation of defects in steel. In this report, he also discusses the validity of the defect creation model. He reports the comparison between experimental and theoretical results of the dose influence, the description of steel irradiations, the comparison of the experimental and computed C coefficient, the calculation of B coefficients for different types of steel, and discusses the importance of thermal neutrons in damages