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

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

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.

Original languageEnglish
Title of host publicationMaterials and Fabrication
PublisherAmerican Society of Mechanical Engineers (ASME)
ISBN (Electronic)9780791851685
DOIs
Publication statusPublished - 2018
EventASME 2018 Pressure Vessels and Piping Conference, PVP 2018 - Prague, Czech Republic
Duration: 2018 Jul 152018 Jul 20

Publication series

NameAmerican Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP
Volume6B-2018
ISSN (Print)0277-027X

Other

OtherASME 2018 Pressure Vessels and Piping Conference, PVP 2018
Country/TerritoryCzech Republic
CityPrague
Period18/7/1518/7/20

ASJC Scopus subject areas

  • Mechanical Engineering

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