Degradations of thermal shock resistance and fracture toughness of neutron irradiated reactor graphite.

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概要

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• This paper deals with the irradiation effects on the thermal shock resistance Δ= σ<SUB>t</SUB>k/Eα (σ<SUB>t</SUB>: tensile strength, k: thermal conductivity, E: Young's modulus, α: thermal expansivity) and the thermal shock fracture toughness ∇= K<SUB>Ic</SUB>k/Eα (K<SUB>Ic</SUB>: fracture tough-ness value of mode I) in addition to other mechanical properties such as the diametral compressive strength and fracture toughness of two kinds of near isotropic graphite neutron irradiated at 750 1, 000°C to a dose of (1.1 1.5) × 10<SUP>21</SUP> n/cm<SUP>2</SUP> (> 29 fJ). One of the graphite specimen is an isostatically molded graphite IG-11 with fine grain petroleum coke and the other is a binderless molded graphite HCB-18 which was prepared using mesophase pitch carbon with very fine grain size. These measurements are carried out by means of disk testing method developed by us. Results show that both the thermal shock resistance and the thermal shock fracture toughness of the two kinds of graphite after irradiation decrease considerably in contrast with increasing trends of the usual mechanical strengths.

• 一般社団法人 日本原子力学会の論文

著者

• Kurumada Akira

  Faculty Of Engineering Ibaraki University

• Sato Sennosuke

  Faculty Of Engineering The University Of Ibaraki Hitachi.

• Kawamata Kiyohiro

  Faculty Of Engineering Ibaraki University

• ISHIDA Ryohei

  Faculty of Engineering, University of Osaka Prefecture

• AWAJI Hideo

  Japan Fine Ceramics Center

• SATO Sennosuke

  Faculty of Engineering, Ibaraki University

• UGACHI Hirokazu

  Faculty of Engineering, Ibaraki University

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• An Approach to Detecting the Brittle Transition Temperature of Steels by Means of Hardness Testing and Its Applications
• Effect of Neutron Irradiation on the Microstructures and Tensile Properties of Different Carbon Fibers
• Degradations of thermal shock resistance and fracture toughness of neutron irradiated reactor graphite.

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