Characterization of internal and intergranular oxidation in Alloy 690 exposed to simulated PWR primary water and its implications with regard to stress corrosion cracking

2019 ◽  
Vol 157 ◽  
pp. 109922 ◽  
Author(s):  
Yun Soo Lim ◽  
Dong Jin Kim ◽  
Sung Woo Kim ◽  
Seong Sik Hwang ◽  
Hong Pyo Kim
Author(s):  
J. M. Boursier ◽  
F. Vaillant ◽  
B. Yrieix

In 1991, a vessel head penetration was found leaking at Bugey 3 plant during the hydrotest. Metallurgical investigations confirmed that this problem was again related to primary water stress corrosion cracking of alloy 600. Moreover, the main crack initiated in the base metal of the penetration (alloy 600) has also propagated in the weld metal in alloy 182. More recently, stress corrosion cracking in alloy 182 has been found on welds of U.S. plants. SCC susceptibility of alloy 182 has been evidenced by several laboratories. In France, all original vessel heads using alloy 600 have been or will be replaced with penetrations in alloy 690 (with 30% chromium). With respect to substitution materials, ELECTRICITE´ DE FRANCE has undertaken a large R&D study focusing on the development of new weld metals. The aim of this study was to identify new materials that will be able to weld alloy 690. Weld metals containing 15 to 30% Chromium have been studied. This paper presents an overview of the main results obtained on 19% Cr, 26% Cr and 30% Cr alloys with respect to alloy 182 (15% Cr). Firstly, the weldability of weld metals has been studied focusing on the susceptibility to hot cracking. Secondly, the resistance to thermal ageing has been investigated in order to detect any long term ordering of the solid solution Ni-Cr that could induce embrittlement. Hardness tests, Charpy tests and resistivity measurements did not show any effect of ageing up to 60,000 hours at 360°C. Thirdly, stress corrosion cracking susceptibility in primary water at 360°C has been evaluated during constant load tests, RUB tests, slow strain rate tests. No cracking was observed on material containing more than 26% Cr for both initiation and propagation. Finally, a life assessment was performed for all weld materials with respect to alloy 182.


Author(s):  
B. Alexandreanu ◽  
O. K. Chopra ◽  
W. J. Shack

Alloys 690 and 152 are the replacement materials of choice for Alloys 600 and 182, respectively. The latter two alloys are used as structural materials in pressurized water reactors (PWRs) and have been found to undergo stress corrosion cracking (SCC). The objective of this work is to determine the crack growth rates (CGRs) in a simulated PWR water environment for the replacement alloys. The study involved Alloy 690 cold-rolled by 26% and a laboratory-prepared Alloy 152 double-J weld in the as-welded condition. The experimental approach involved pre-cracking in a primary water environment and monitoring the cyclic CGRs to determine the optimum conditions for transitioning from the fatigue transgranular to intergranular SCC fracture mode. The cyclic CGRs of cold-rolled Alloy 690 showed significant environmental enhancement, while those for Alloy 152 were minimal. Both materials exhibited SCC of 10−11 m/s under constant loading at moderate stress intensity factors. The paper also presents tensile property data for Alloy 690TT and Alloy 152 weld in the temperature range 25–870°C.


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