Evaluation of tensile strength of nuclear fuel samples

International Conference on Synthesis and Consolidation of Powder Materials

Goltsev, V.Y.^1^2 ; Osintsev, A.V.^1

National Research Nuclear University, MEPhI, Moscow

115409, Russia^1

Merzhanov Institute of Structural Macrokinetics and Materials Science, Russian Academy of Sciences, Chernogolovka

142432, Russia^2

关键词: Brazilian test;    Calculation formula;    Deformation and fracture;    Material-based;    Model materials;    On-resistance;    Specimen sizes;    Test technology;   

Others  :  https://iopscience.iop.org/article/10.1088/1757-899X/558/1/012013/pdf
DOI  :  10.1088/1757-899X/558/1/012013

来源: IOP

【 摘 要 】

For estimation of the strength of the nuclear fuel material as well and for further refinement of nuclear fuel test technology we propose to use small discoid samples, similar in shape to the elements of nuclear fuel in the context of "Brazilian test". We present here the results of testing small discoid specimens with and without center hole, made of brittle materials, such as cast iron and graphite (both being considered as possible model materials for the nuclear fuel). We compared these materials to nuclear fuel itself (as represented by uranium dioxide). The type of deformation and fracture found in samples made from cast iron suggests that this material cannot be used as a model for the nuclear fuel. In addition, the effect of the specimen size on resistance to destruction was investigated. The results obtained in tests on samples of graphite ARV-1 were in good agreement with the results of tests on uranium dioxide. Using the data obtained in this study, a calculation formula for determining the strength of the nuclear fuel material based on the "Brazilian test" results is proposed.