Fe welding residual stress analysis and validation for spent nuclear fuel canisters

Jae Min Gim; Ji Soo Kim; Yun Jae Kim; Poh Sang Lam

Fe welding residual stress analysis and validation for spent nuclear fuel canisters

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

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

Abstract

Spent Nuclear Fuel (SNF) Canisters are large welded stainless steel structures without post-weld heat treatment, possibly leaving large welding residual stresses (WRS). For CISCC assessments for SNF canisters, the estimation of the weld residual stress accurately is very important because tensile stress can make crack initiate. In this paper, the welding procedure for the SNF canisters is simulated through a FE analysis. Two-dimensional FE WRS analysis is performed for both longitudinal welding and circumferential welding. To simulate the welding procedure, heat analysis and stress analysis are conducted separately. The results are compared with the experimental mock-up canister WRS data conducted at the Sandia National Laboratories. It seems that FEA could sufficiently confirm the experimental data.

Original language	English
Title of host publication	Materials and Fabrication
Publisher	American Society of Mechanical Engineers (ASME)
ISBN (Electronic)	9780791851685
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

Cite this

Fe welding residual stress analysis and validation for spent nuclear fuel canisters. / Gim, Jae Min; Kim, Ji Soo; Kim, Yun Jae 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

Gim, JM, Kim, JS, Kim, YJ & Lam, PS 2018, Fe welding residual stress analysis and validation for spent nuclear fuel canisters. 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.

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abstract = "Spent Nuclear Fuel (SNF) Canisters are large welded stainless steel structures without post-weld heat treatment, possibly leaving large welding residual stresses (WRS). For CISCC assessments for SNF canisters, the estimation of the weld residual stress accurately is very important because tensile stress can make crack initiate. In this paper, the welding procedure for the SNF canisters is simulated through a FE analysis. Two-dimensional FE WRS analysis is performed for both longitudinal welding and circumferential welding. To simulate the welding procedure, heat analysis and stress analysis are conducted separately. The results are compared with the experimental mock-up canister WRS data conducted at the Sandia National Laboratories. It seems that FEA could sufficiently confirm the experimental data.",

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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 {\textcopyright} 2018 ASME.; ASME 2018 Pressure Vessels and Piping Conference, PVP 2018 ; Conference date: 15-07-2018 Through 20-07-2018",

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AU - Gim, Jae Min

AU - Kim, Ji Soo

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AU - Lam, Poh Sang

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N2 - Spent Nuclear Fuel (SNF) Canisters are large welded stainless steel structures without post-weld heat treatment, possibly leaving large welding residual stresses (WRS). For CISCC assessments for SNF canisters, the estimation of the weld residual stress accurately is very important because tensile stress can make crack initiate. In this paper, the welding procedure for the SNF canisters is simulated through a FE analysis. Two-dimensional FE WRS analysis is performed for both longitudinal welding and circumferential welding. To simulate the welding procedure, heat analysis and stress analysis are conducted separately. The results are compared with the experimental mock-up canister WRS data conducted at the Sandia National Laboratories. It seems that FEA could sufficiently confirm the experimental data.

AB - Spent Nuclear Fuel (SNF) Canisters are large welded stainless steel structures without post-weld heat treatment, possibly leaving large welding residual stresses (WRS). For CISCC assessments for SNF canisters, the estimation of the weld residual stress accurately is very important because tensile stress can make crack initiate. In this paper, the welding procedure for the SNF canisters is simulated through a FE analysis. Two-dimensional FE WRS analysis is performed for both longitudinal welding and circumferential welding. To simulate the welding procedure, heat analysis and stress analysis are conducted separately. The results are compared with the experimental mock-up canister WRS data conducted at the Sandia National Laboratories. It seems that FEA could sufficiently confirm the experimental data.

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T3 - American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP

BT - Materials and Fabrication

PB - American Society of Mechanical Engineers (ASME)

T2 - ASME 2018 Pressure Vessels and Piping Conference, PVP 2018

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ER -

Fe welding residual stress analysis and validation for spent nuclear fuel canisters

Abstract

Publication series

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Bibliographical note

ASJC Scopus subject areas

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