Progress report on stress intensity factor and J-integral estimation for nuclear fuel canisters under mechanical loading

Ji Su Kim, Yun Jae Kim, Jae Min Gim, Poh Sang Lam

研究成果: Conference contribution

抄録

Due to the interaction of welding residual stress (WRS) and salt environment, cracks can be generated and grow in the Spent Nuclear Fuel (SNF) Canisters. In this paper, two fracture mechanics parameters, stress intensity factor and J-integral, for the canisters with axial cracks subjected to the mechanical loading are calculated by finite element analysis. The structural integrity assessment codes, API 579-1 and R6, are used to verify the procedure. For every external surface crack and through-wall crack, the stress intensity factor follows well the existing evaluation codes, API 579-1. The reference stress-based J-integral prediction of R6 procedure is the most accurate to use the tresca-based limit load as the reference stress.

本文言語English
ホスト出版物のタイトルMaterials and Fabrication
出版社American Society of Mechanical Engineers (ASME)
ISBN(電子版)9780791851685
DOI
出版ステータスPublished - 2018
イベントASME 2018 Pressure Vessels and Piping Conference, PVP 2018 - Prague, Czech Republic
継続期間: 2018 7 152018 7 20

出版物シリーズ

名前American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP
6B-2018
ISSN(印刷版)0277-027X

Conference

ConferenceASME 2018 Pressure Vessels and Piping Conference, PVP 2018
CountryCzech Republic
CityPrague
Period18/7/1518/7/20

ASJC Scopus subject areas

  • Mechanical Engineering

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