Deployment of Laser Peening to Prevent CISCC of Nuclear Fuel Dry Storage Canisters

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.

2006 ◽  
Vol 75 (7) ◽  
pp. 579-582 ◽  
Author(s):  
Yuji SANO ◽  
Naruhiko MUKAI ◽  
Minoru OBATA ◽  
Hiromi KATO ◽  
Tetsuo YAMAMOTO

2005 ◽  
Vol 33 (7) ◽  
pp. 444-451 ◽  
Author(s):  
Naruhiko MUKAI ◽  
Yuji SANO ◽  
Masaki YODA ◽  
Itaru CHIDA ◽  
Takuya UEHARA ◽  
...  

Author(s):  
Takuya Uehara ◽  
Masaki Yoda ◽  
Yuji Sano ◽  
Naruhiko Mukai ◽  
Itaru Chida ◽  
...  

Laser peening introduces compressive residual stress on metal surface by irradiating laser pulses underwater without any surface preparations. The process utilizes the impulsive effect of high-pressure plasma generated through ablative interaction of each laser pulse with material. Laser peening systems, which deliver laser pulses with mirrors or through an optical fiber, were developed and have been applied to preventive maintenance against stress corrosion cracking (SCC) in nuclear power reactors since 1999. Each system was composed of laser oscillators, a beam delivery system, a laser irradiation head, remote handling equipment and a monitor/control system. Beam delivery with mirrors was accomplished through alignment/tracking functions with sufficient accuracy. Reliable fiber-delivery was attained by the development of a novel input coupling optics and an irradiation head with auto-focusing. At present, we are developing a newer concept and the prototype system has been just completed, which is extremely small, reliable and easy-handled.


Author(s):  
Frederick W. Brust ◽  
R. E. Kurth ◽  
D. J. Shim ◽  
David Rudland

Risk based treatment of degradation and fracture in nuclear power plants has emerged as an important topic in recent years. One degradation mechanism of concern is stress corrosion cracking. Stress corrosion cracking is strongly driven by the weld residual stresses (WRS) which develop in nozzles and piping from the welding process. The weld residual stresses can have a large uncertainty associated with them. This uncertainty is caused by many sources including material property variations of base and welds metal, weld sequencing, weld repairs, weld process method, and heat inputs. Moreover, often mitigation procedures are used to correct a problem in an existing plant, which also leads to uncertainty in the WRS fields. The WRS fields are often input to probabilistic codes from weld modeling analyses. Thus another source of uncertainty is represented by the accuracy of the predictions compared with a limited set of measurements. Within the framework of a probabilistic degradation and fracture mechanics code these uncertainties must all be accounted for properly. Here we summarize several possibilities for properly accounting for the uncertainty inherent in the WRS fields. Several examples are shown which illustrate ranges where these treatments work well and ranges where improvement is needed. In addition, we propose a new method for consideration. This method consists of including the uncertainty sources within the WRS fields and tabulating them within tables which are then sampled during the probabilistic realization. Several variations of this process are also discussed. Several examples illustrating the procedures are presented.


Author(s):  
Deok Hyun Lee ◽  
Do Haeng Hur ◽  
Myung Sik Choi ◽  
Kyung Mo Kim ◽  
Jung Ho Han ◽  
...  

Occurrences of a stress corrosion cracking in the steam generator tubes of operating nuclear power plants are closely related to the residual stress existing in the local region of a geometric change, that is, expansion transition, u-bend, ding, dent, bulge, etc. Therefore, information on the location, type and quantitative size of a geometric anomaly existing in a tube is a prerequisite to the activity of a non destructive inspection for an alert detection of an earlier crack and the prediction of a further crack evolution [1].


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