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

doi:10.1115/pvp2018-84966

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 proceeding › Conference 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 language	English
Title of host publication	Materials and Fabrication
Publisher	American Society of Mechanical Engineers (ASME)
ISBN (Electronic)	9780791851685
DOIs	https://doi.org/10.1115/pvp2018-84966
Publication status	Published - 2018
Event	ASME 2018 Pressure Vessels and Piping Conference, PVP 2018 - Prague, Czech Republic Duration: 2018 Jul 15 → 2018 Jul 20

Publication series

Name	American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP
Volume	6B-2018
ISSN (Print)	0277-027X

Other

Other	ASME 2018 Pressure Vessels and Piping Conference, PVP 2018
Country/Territory	Czech Republic
City	Prague
Period	18/7/15 → 18/7/20

Bibliographical note

Funding Information:
This research was supported by National Research Foundation of Korea (NRF) funded by the Ministry of Science, ICT and Future Planning. (NRF-2016M2A8A1952771)

Publisher Copyright:
Copyright © 2018 ASME.

ASJC Scopus subject areas

Mechanical Engineering

Access to Document

10.1115/pvp2018-84966

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 (American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP; Vol. 6B-2018). American Society of Mechanical Engineers (ASME). https://doi.org/10.1115/pvp2018-84966

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 et al.
Materials and Fabrication. American Society of Mechanical Engineers (ASME), 2018. (American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP; Vol. 6B-2018).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

Kim, JS, Kim, YJ, 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. American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP, vol. 6B-2018, American Society of Mechanical Engineers (ASME), ASME 2018 Pressure Vessels and Piping Conference, PVP 2018, Prague, Czech Republic, 18/7/15. https://doi.org/10.1115/pvp2018-84966

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

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.",

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N2 - 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.

AB - 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.

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ER -

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

Abstract

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ASJC Scopus subject areas

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