Used Fuel Disposition Campaign - Embrittlement and DBTT of High-Burnup PWR Fuel Cladding Alloys

Billone, M.C.; Burtseva, Tatyana; Han, Zhenlai; Y., Liu, Y.; NE,

doi:10.2172/1096165

Cited by 10 publications

(7 citation statements)

References 8 publications

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“…Two samples with about the same RHCF were chosen for evaluation of radial hydride metrics. On the basis of previously reported results [10], the ZIRLO™ and M5® rodlets had 30 to 35% RHCF, but they differed in DBTT values by >105°C. Figure 5 Used Fuel Disposition Campaign Sample 648C7 was retrieved from storage, re-ground, re-polished, and carefully re-etched.…”

Section: Radial Hydride Metricsmentioning

confidence: 56%

“…Details of rodlet fabrication are given in Ref. 10. Prior to rodlet pressurization, the outer diameter was measured for each corroded segment at two orientations (90° apart) and at three axial locations.…”

Section: Test Protocolmentioning

confidence: 99%

“…In Used Fuel Disposition Campaign and M5®. These data are important not only for determining the degrading effects of drying and early stage storage, but also for serving as reference properties for future evaluations of the effects of drying storage on these cladding alloys [7][8][9]. Reference 10 includes all Argonne data generated through September 2013, including additional DOE-sponsored test results for HBU ZIRLO™ and M5® following cooling from 400°C and lower hoop stress levels (80 to 90 MPa).…”

Section: Introductionmentioning

confidence: 99%

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Effects of Multiple Drying Cycles on High-Burnup PWR Cladding Alloys

Billone¹,

Burtseva²,

Han³

et al. 2014

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The purpose of this research effort is to determine the effects of canister/cask vacuum drying and storage on radial hydride precipitation in high-burnup (HBU) pressurized water reactor (PWR) cladding alloys during cooling for a range of peak drying-storage temperatures, internal gas pressures, and hoop stresses. The HBU PWR cladding alloys have a wide range of hydrogen contents and varying hydride morphology after in-reactor service. Radial hydrides are a potential embrittlement mechanism for HBU cladding subjected to hoop-stress loading, which may be significant during normal cask transport. Ring compression tests (RCTs), which simulate pinch-type loading at grid spacers, are used to determine cladding ductility as a function of RCT temperature and the ductile-to-brittle transition temperature (DBTT). Previous tests were conducted with pressurized and sealed cladding rodlets heated to 400°C (the NRC ISG-11, Rev. 3, limit for all fuel burnups under normal conditions of storage and short-term loading operations) and cooled slowly at 5°C/h. Following this drying-storage simulation, the DBTT for HBU M5® decreased from 80°C to 70°C to <20°C as the peak hoop stress decreased from 140 MPa to 110 MPa to 90 MPa. Under similar drying-storage conditions, the DBTT for HBU ZIRLO™ decreased from 185°C to 125°C to 20°C to <20°C as the peak cladding hoop stress decreased from 140 MP to 110 MPa to 90 MPa to 80 MPa. These tests were conducted with a single heating-cooling cycle as simulation of the vacuum drying process with one drying cycle. (ISG-11, Rev. 3 allows <10 drying cycles, with cladding temperature variations that are less than 65°C each.)To examine the effects of multiple drying cycles at peak cladding temperature of 400°C, the HBU ZIRLO™ test at 90 MPa was repeated with three heating-cooling cycles and with a 100°C temperature drop at 5°C/h for the first two cycles. Temperature cycling was found to have no apparent effect on the extent of radial hydride precipitation and the resulting DBTT, even though dissolution and re-precipitation of hydrides occurred during each of the drying cycles.

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Section: Radial Hydride Metricsmentioning

confidence: 56%

Section: Test Protocolmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Effects of Multiple Drying Cycles on High-Burnup PWR Cladding Alloys

Billone¹,

Burtseva²,

Han³

et al. 2014

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“…In the as-irradiated condition HBU ZIRLO™ had relatively high ductility (6% to >11%) for tests conducted at RT displacement rates of 0.05 mm/s to 50 mm/s and at 5 mm/s and RT to 150°C. For an 80-MPa peak RHT hoop stress, radial hydrides were short (9±4% RHCF) and ductility values were moderately high at RT and 60°C and high (>9%) at 90°C and 150°C [6,9]. Thus, for peak RHT conditions of 400°C and ≤80 MPa, the corresponding DTT would be <20°C.…”

Section: Hbu Zirlo™mentioning

confidence: 96%

Effects of Radial Hydrides on PWR Cladding Ductility following Drying and Storage

Billone

Burtseva

García-Infanta

2017

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The purpose of this research effort is to determine the effects of canister and/or cask drying, transfer and storage on radial hydride precipitation in, and potential embrittlement of, high-burnup (HBU) pressurized water reactor (PWR) cladding alloys during cooling for a range of peak drying-storage temperature (PCT) values and hoop stresses. Extensive radial-hydride precipitation could lower failure hoop stresses and strains, relative to limits established for as-irradiated cladding from discharged fuel rods, at temperatures below the ductility transition temperature (DTT), which has been referred to as the ductile-to-brittle transition temperature (DBTT) in previous reports. During post-storage transport, hoop stresses will be induced by "pinch-type" loading at grid spacers. Such loading is considered to be mild for normal conditions of transport and more severe for hypothetical accident conditions.

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“…Eight of these samples were from as-irradiated and heat-treated sibling pin cladding [7]. The other eight were from HBU fuel-rod cladding tested prior to the sibling pin work [14,15]. Test results that indicated cracking and/or significant loading lags were not included.…”

Section: Unloading Slopementioning

confidence: 99%

Ductility of Zircaloy-4 Sibling Pin Cladding

Billone¹,

Burtseva²,

Chen³

et al. 2023

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The High Burnup Spent Fuel Data Project is a joint partnership between the Electric Power Research Institute and SFWST to perform large-scale demonstration and laboratoryscale testing of HBU fuels (exceeding 45 gigawatt-days per metric ton of uranium, GWd/MTU) to determine their performance during extended storage. For laboratory-scale testing, 25 HBU sibling pins (i.e., fuel rods) irradiated in a pressurized water reactor have been provided. These fuel rods were either extracted from fuel assemblies loaded into the Data Project cask or from assemblies with irradiation histories similar to assemblies loaded into the cask. ANL's mission is to characterize and test defueled cladding samples to determine if cladding retains ductility following drying and long-term storage. Ductility retention is desirable during all phases of storage and transportation as plastic flow limits crack growth by reducing stresses at crack tips. The ANL effort is a continuation of SFWST-sponsored research performed from 2011-2019 with defueled Zircaloy-4 (Zry-4), ZIRLO®, and M5® cladding from lead-testassembly fuel rods irradiated to 63─72 GWd/MTU rod-average burnup. In FY2020-21, room temperature (RT) ductility was determined for sibling-pin ZIRLO® and M5® cladding in the as-irradiated condition and following cooling from simulated drying at 400°C peak cladding temperature and 400°C hoop stresses of 66 MPa and 52 MPa, respectively. At these low peak hoop stress levels, radial hydrides did not cause embrittlement or a significant decrease in ductility. FY2022-23 Accomplishments• As-irradiated low-tin (LT) Zry-4 with high hydrogen content was shown to have ductility at room temperature (RT), as well as at 90°C and 120°C. These results were compared to pre-sibling-pin results for Zry-4 and ZIRLO® cladding with >600 weight parts per million hydrogen.• Zry-4 cladding samples with high hydrogen content were subjected to full-length heat treatment (FHT) by Oak Ridge National Laboratory (ORNL) prior to ductility testing at ANL. The FHT included an 8-hour hold time at 400°C followed by slow cooling at ≈4°C/h. The hoop stress at 400°C for the segment sent to ANL was about 85 MPa. Two of the samples tested at RT were brittle and two had very low ductility. At test temperatures of 120°C and 150°C, ductility values were ≥6%.

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Used Fuel Disposition Campaign - Embrittlement and DBTT of High-Burnup PWR Fuel Cladding Alloys

Abstract: FCRD-UFD-2013-000401 ANL-13/16 DISCLAIMER This information was prepared as an account of work sponsored by an agency of the U.

Cited by 10 publications

References 8 publications

Effects of Multiple Drying Cycles on High-Burnup PWR Cladding Alloys

Effects of Multiple Drying Cycles on High-Burnup PWR Cladding Alloys

Effects of Radial Hydrides on PWR Cladding Ductility following Drying and Storage

Ductility of Zircaloy-4 Sibling Pin Cladding

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