Modeling of Zircaloy Stress-Corrosion Cracking: Texture Effects and Dry Storage Spent Fuel Behavior

2008 ◽  
pp. 595-595-32 ◽  
Author(s):  
A Tasooji ◽  
RE Einziger ◽  
AK Miller
Author(s):  
Lloyd Hackel ◽  
Jon Rankin ◽  
Matt Walter ◽  
C. Brent Dane ◽  
William Neuman ◽  
...  

Abstract By generating very deep levels of compressive stress, laser peening can eliminate stress corrosion cracking of materials of use in the nuclear industry; tested materials include Alloys N06600 (Inconel 600), N06690 (Inconel 690), N06022 (Alloy C22) and stainless steels K44220 (300M), S30400 (304) and S31600 (316L). In this work we take a further step in direct application to the welds of multi-purpose canisters (MPCs) employed for dry storage of spent fuel at nuclear plants. This storage is a temporary approach awaiting interim or permanent storage.. For storage in coastal, lakeside and even humid environments, air-entrained chlorides can make the canister welds susceptible to pitting and chloride induced stress corrosion cracking (CISCC). Using ASTM G36 (2013) accelerated corrosive testing we evaluated CISCC lifetimes of welded 316L stainless steel canister plates configured to MPC geometry showing in excess of 19 times lifetime increase of laser peened panel sections vs. those left as-welded. Specifically cracks never developed within and were arrested when propagating into the laser peened area. We measured residual stress in test plates and related it to calculations of stress intensity and depth expected in the full canister geometry. We discuss the relevance of stress depth to pitting depth and crack growth rates. Our two-dimensional stress mapping shows that high energy laser peening provides deep (> 5 mm) plastic compression in the canister material and geometry. In parallel, as we gained customer and NRC approvals, we developed and deployed the hardware and control technology that enabled a transportable system to peen canisters welds during the fabrication process. The canisters are now loaded or in process of being loaded at the San Onofre Nuclear Power Plant.


2019 ◽  
Vol 19 ◽  
pp. 346-361 ◽  
Author(s):  
Lloyd Hackel ◽  
Jon Rankin ◽  
Matt Walter ◽  
C Brent Dane ◽  
William Neuman ◽  
...  

Author(s):  
S. W. Cho ◽  
W. G. Yi ◽  
N. Mohr ◽  
A. Amanov ◽  
C. Stover ◽  
...  

Abstract It is necessary for nuclear power plant operation and spent fuel canisters to provide a sound technical basis for the safety and security of long-term operation and storage respectively. A new code case for mitigation of Primary Water Stress Corrosion Cracking (PWSCC) and Chloride Induced Stress Corrosion Cracking (CISCC) in Section III components by using an advanced surface stress improvement technology (ASSIT) is being developed by Task Group ASSIT which is one of the task groups under the ASME (The American Society of Mechanical Engineers). The necessary technical reports supporting this code case are being developed as part of joint research projects conducted by Doosan Heavy Industries and Construction (DOOSAN), Electric Power Research Institute (EPRI) and Sun Moon University (SMU). A well-known approach to prevent PWSCC and CISCC are to be performed using materials resistant to PWSCC and CISCC. The objective is to eliminate residual tensile stresses, or to induce compressive residual stress using ASSIT methods such as laser peening, water jet/cavitation peening, ultrasonic peening and ultrasonic nanocrystal surface modification (UNSM). Performance and measurement criteria for mitigation of PWSCC by ASSIT will be established based on the magnitude of surface stress and depth of compressive residual stress, sustainability, inspectability and lack of adverse effects. Additionally, for mitigation of CISCC by ASSIT, the evaluation of chloride induced corrosion pitting, the depth and density of corrosion pits and stress corrosion crack initiation and growth under chloride salt chemistry conditions are also being examined. This paper explains the approach, and progress of testing and analysis. The results and details from testing and analysis will be presented in a future PVP paper upon completion.


Author(s):  
John E. Broussard ◽  
Shannon Chu ◽  
Kevin Fuhr

A probabilistic model was developed that considers the likelihood of through-wall penetration of chloride-induced stress corrosion cracking (CISCC) in austenitic stainless steel canisters and compares different population-based sample inspection regimes. This paper describes the inputs and methods used to simulate multiple canisters with a range of susceptibilities. This paper also summarizes results of key illustrative cases.


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