FE Welding Residual Stress Analysis and Validation for Spent Nuclear Fuel Canisiters

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

doi:10.1115/pvp2018-84857

Cited by 4 publications

(6 citation statements)

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“…Their experimental data confirmed that most of the as-welded residual stresses were retained in the sectioned plate. Therefore, it is reasonable to assume that the residual stresses in the large SRNL plate would be similar to those reported by Enos and Bryan (experiment) [15] and by Gim (finite element analysis) [32].…”

Section: Large Plate Demonstration Of Cisccsupporting

confidence: 65%

“…14, the loading experienced by the bolt-load CT is "Bolt Load + RS3" or "Bolt-Load+RS4," where the "bolt load" is the tensile stress exerted by tightening the instrumented bolt; RS3 represents the WRS perpendicular to the circumferential weld; and RS4 is the WRS parallel to the axial weld. Note that RS3 and RS4 have been obtained experimentally [15] and numerically by finite element simulation [32] (see Fig. 15).…”

Section: Methodsmentioning

confidence: 81%

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Crack Growth Rate and Large Plate Demonstration of Chloride-induced Stress Corrosion Cracking in Spent Nuclear Fuel Storage Canisters

Lam

Duncan

Sindelar

2019

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This report describes the body of work involving testing and analyses performed in FY18 and FY19 at the Savannah River National Laboratory and at Korea University to determine chlorideinduced stress corrosion crack (CISCC) growth rates in weldments of austenitic stainless steel plate material. The primary work involved: several separate crack growth rate test campaigns with new testing setups using laboratory-scale corrosion specimens;  analyses to estimate the stress intensity factors for flaws postulated to be present in the residual stress fields of axial and circumferential weldments in a prototypic dry storage canister; and  establishment of a "large plate" (approximately 51×46 cm with thickness 16 mm and weight about 30 kg) CISCC test that uses a plate with a circumferential weldment harvested from the Sandia National Laboratories' full-size mockup dry storage canister.The tests for crack growth rate were conducted on ASTM E1861 bolt-load compact tension specimens in a setup designed to allow initially dried salt deposits to deliquesce and infuse the brine to the crack front under conditions relevant to the canister storage environments (e.g., temperature and humidity). The crack growth rate test results matched previous experimental data in the open literature. These literature data had been compiled by SNL and EPRI to develop a temperature-dependent (K-insensitive) crack growth rate model to support flaw disposition in the ASME Boiler and Pressure Vessel Section XI Code Case N-860, "Examination Requirements and Acceptance Standards for Spent Nuclear Fuel Storage and Transportation Containment Systems."The knowledge of the salt, temperature, humidity conditions for CISCC including the threshold stress intensity factor, KISCC, were used to setup the large plate test in which a set of partthrough-wall and through-wall electrical discharge machined (EDM) defects were positioned in the weld residual stress field of the welded plate material from the mockup canister. A salt solution was applied to this plate specimen with an air-brush spray, then dried, and then exposed to a constant 75% RH condition at an ambient room temperature of 22 °C. The salt loading and environmental condition is expected to be aggressive to cause CISCC. The visual results at the surface of the plate show corrosion product staining (brown rust appearance) but with no CISCC emanating from the machined notches after approximately 5 months exposure to date.The plate test will continue in FY20 and phased-array ultrasonic testing and other NDE techniques will be applied to identify and characterize CISCC that may emanate from the machined defects. The notches and any CISCC from them will be sectioned at the conclusion of the test to verify NDE characterization, and to develop effective through-wall crack growth rates from cracks that would likely be branched.

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Section: Large Plate Demonstration Of Cisccsupporting

confidence: 65%

Section: Methodsmentioning

confidence: 81%

Crack Growth Rate and Large Plate Demonstration of Chloride-induced Stress Corrosion Cracking in Spent Nuclear Fuel Storage Canisters

Lam

Duncan

Sindelar

2019

Self Cite

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“…Their experimental data confirmed that most of the as-welded residual stresses were retained in the sectioned plate. Therefore, it is reasonable to assume that the residual stresses in the large plate would be similar to those reported by Enos and Bryan (experiment) [1] and by Gim et al (finite element simulation) [11].…”

Section: Materials and Experimental Setupsupporting

confidence: 64%

CISCC Experiment of a Large Plate Sectioned From a Spent Nuclear Fuel Canister

Duncan

Lam

Sindelar

2020

Volume 6: Materials and Fabrication

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As a long-term demonstration of chloride-induced stress corrosion cracking (CISCC) driven by welding residual stress (WRS), a large section (approximately 51 × 46 cm with thickness 16 mm and weight about 30 kg), which contains a circumferential weld, was cut from a full-size mockup canister. Through-wall and part-through-wall (surface) starter cracks, either parallel or perpendicular to the weld, were fabricated with electrical discharge machining (EDM) in the weld region. The stress intensity factors (KI) for each machined starter crack under canister WRS were estimated so as to provide insight into the propensity for crack initiation and growth. Dry salt was applied over these machined cracks on the surface of the large plate and natural deliquescence was allowed to take place at room temperature and 75% RH. This test has been on-going for ten months and the evolution of general corrosion near the starter cracks is monitored and documented; no CISCC has been observed. Two EDM starter cracks have been isolated for five months for a simultaneous experiment with extra salt loading; additional deliquescence and significant corrosion activity have been observed.

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“…The 4 th -order polynomial fit reported here was obtained by Korea University under DOE I-NERI/USA-ROK program [4]. These residual stresses were also determined using the finite element method [15] welding procedure documented in a previous report [6], and are in good agreement with the experimental results. The designations of these welding residual stresses are shown in Figure 3, where RS2 is the WRS component parallel to the weld and tends to open an axial crack, and RS3 is the WRS perpendicular to the weld and is responsible for opening a circumferential crack.…”

Section: Welding Residual Stresssupporting

confidence: 59%

Large Plate Experiment of Chloride-induced Stress Corrosion Cracking in Spent Nuclear Fuel Storage Canisters

Duncan

Ward

Perez

et al. 2020

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FE Welding Residual Stress Analysis and Validation for Spent Nuclear Fuel Canisiters

Cited by 4 publications

References 0 publications

Crack Growth Rate and Large Plate Demonstration of Chloride-induced Stress Corrosion Cracking in Spent Nuclear Fuel Storage Canisters

Crack Growth Rate and Large Plate Demonstration of Chloride-induced Stress Corrosion Cracking in Spent Nuclear Fuel Storage Canisters

CISCC Experiment of a Large Plate Sectioned From a Spent Nuclear Fuel Canister

Large Plate Experiment of Chloride-induced Stress Corrosion Cracking in Spent Nuclear Fuel Storage Canisters

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