Study of Mechanical Properties, Microstructure, and Residual Stresses of AISI 304/304L Stainless Steel Submerged Arc Weld for Spent Fuel Dry Storage Systems

Author:

Tang Wei1,Chatzidakis Stylianos2ORCID,Schrad Caleb Matthew3,Miller Roger G.1,Howard Robert2

Affiliation:

1. Materials Science and Technology Division, Oak Ridge National Laboratory, 1 Bethel Valley Road, Oak Ridge, TN 37831, USA

2. Nuclear Energy and Fuel Cycle Division, Oak Ridge National Laboratory, 1 Bethel Valley Road, Oak Ridge, TN 37831, USA

3. Department of Arts and Sciences, Grace College, 1 Lancer Wy, Winona Lake, IN 46590, USA

Abstract

The confinement boundaries of spent nuclear fuel (SNF) canisters are typically fusion welded. Welded microstructures, strain hardening, and residual stresses combined with a chemically aggressive, chloride-rich environment led to concerns that the welded canister may be susceptible to chloride-induced stress corrosion cracking (CISCC). A comprehensive understanding of the modification of stainless steel (SS) metallurgical and mechanical properties by fusion welding could accelerate the predictive analysis of CISCC susceptibility. This paper describes a submerged arc welding (SAW) procedure that was developed and qualified on 12.7 mm (0.5 in.) thick AISI 304/304L SS to produce joints in a way similar to actual SNF canister manufacturing. This procedure has the potential to reduce the production cost and weld CISCC susceptibility by using fewer welding passes and lower heat input than current industrial applications. Global and local mechanical behaviors and properties, as well as residual stress distributions on the welded joint, were studied. The results indicate that hardness values in the fusion zone (FZ) and heat-affected zone (HAZ) are slightly higher than that of the base metal. Strain localization was presented in the HAZ before the tensile stress reached its maximum value, and then it shifted to the FZ. The specimen finally broke in the FZ. High tensile residual stresses exhibited in the FZ and the nearby HAZ suggest the highest CISCC-susceptible spots. The maximum tensile residual stresses were along the welding direction, indicating that if cracks occur, they would be perpendicular to the welding direction. This study involved developing and qualifying a SAW procedure for SNF canister production. The new procedure yielded cost savings (SAW working efficiency increased by about 80%), improved mechanical properties, and presented moderate residual stresses. Analysis revealed that the welded joint’s low-stress and high-stress damage assessments may be affected by shifts in the strain localization spot under loading.

Funder

Spent Fuel and Waste Disposition Program for the US Department of Energy Office of Nuclear Energy

Publisher

MDPI AG

Reference39 articles.

1. Kadak, A.C., and Yost, K. (2010). Key Issues Associated with Interim Storage of Used Nuclear Fuel, Massachusetts Institute of Technology.

2. Blue Ribbon Committee (2012). Blue Ribbon Commission on America’s Nuclear Future, Blue Ribbon Committee. Report to the Secretary of Energy.

3. United States Nuclear Waste Technical Review Board (2010). Evaluation of the Technical Basis for Extended Dry Storage and Transportation of Used Nuclear Fuel, United States Nuclear Waste Technical Review Board.

4. Chopra, O.K., Diercks, D.R., Fabian, R.R., Han, Z.H., and Liu, Y.Y. (2014). Managing Aging Effects on Dry Cask Storage Systems for Extended Long-Term Storage and Transportation of Used Fuel, Argonne National Laboratory. ANL-13/15 rev. 2.

5. Nuclear Energy Institute (2016). Format, Content and Implementation Guidance for Dry Cask Storage Operations-Based Aging Management, Nuclear Energy Institute. NEI 14-03 rev. 2.

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