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)
Volume6B-2018
ISBN (Electronic)9780791851685
Publication statusPublished - 2018 Jan 1
EventASME 2018 Pressure Vessels and Piping Conference, PVP 2018 - Prague, Czech Republic
Duration: 2018 Jul 152018 Jul 20

Other

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

Fingerprint

Nuclear fuels
Stress intensity factors
Cracks
Application programming interfaces (API)
Spent fuels
Structural integrity
Load limits
Fracture mechanics
Residual stresses
Welding
Salts
Finite element method

ASJC Scopus subject areas

  • Mechanical Engineering

Cite this

Kim, J. S., Kim, Y-J., Gim, J. M., & Lam, P. S. (2018). Progress report on stress intensity factor and J-integral estimation for nuclear fuel canisters under mechanical loading. In Materials and Fabrication (Vol. 6B-2018). American Society of Mechanical Engineers (ASME).

Progress report on stress intensity factor and J-integral estimation for nuclear fuel canisters under mechanical loading. / Kim, Ji Su; Kim, Yun-Jae; Gim, Jae Min; Lam, Poh Sang.

Materials and Fabrication. Vol. 6B-2018 American Society of Mechanical Engineers (ASME), 2018.

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

Kim, JS, Kim, Y-J, Gim, JM & Lam, PS 2018, Progress report on stress intensity factor and J-integral estimation for nuclear fuel canisters under mechanical loading. in Materials and Fabrication. vol. 6B-2018, American Society of Mechanical Engineers (ASME), ASME 2018 Pressure Vessels and Piping Conference, PVP 2018, Prague, Czech Republic, 18/7/15.
Kim JS, Kim Y-J, Gim JM, Lam PS. Progress report on stress intensity factor and J-integral estimation for nuclear fuel canisters under mechanical loading. In Materials and Fabrication. Vol. 6B-2018. American Society of Mechanical Engineers (ASME). 2018
Kim, Ji Su ; Kim, Yun-Jae ; Gim, Jae Min ; Lam, Poh Sang. / Progress report on stress intensity factor and J-integral estimation for nuclear fuel canisters under mechanical loading. Materials and Fabrication. Vol. 6B-2018 American Society of Mechanical Engineers (ASME), 2018.
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