Modeling Structural Loading of used Nuclear Fuel Under Conditions of Normal Transportation

Geelhood, Kenneth J.; Adkins, Harold E.; Sanborn, Scott Edward; Koeppel, Brian J.; Klymyshyn, Nicholas

doi:10.1002/9781119040323.ch9

“…Averages are provided for burnup, cycles to failure, strain, and flexural rigidity for comparison purposes. The results are consistent with previous data for the same size of fuel rods (17 × 17), as shown in Figure 15, although when trended with stress amplitude, as shown in Figure 16, the sister rod fatigue lifetimes appear to be on the lower side of other lifetime estimates, and some data are below the fatigue limit estimates [14,15].…”

Section: Fatigue Testingsupporting

confidence: 92%

Sister Rod Destructive Examinations (FY22)

Montgomery¹,

Bevard²

2023

2

0

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“…Averages are provided for burnup, cycles to failure, strain, and flexural rigidity for comparison purposes. The results are consistent with previous data for the same size of fuel rods (17 × 17), as shown in Figure 14, although when trended with stress amplitude, as shown in Figure 15, the sister rod fatigue lifetimes appear to be on the lower side of other lifetime estimates, and some data are below the fatigue limit estimates [14,15].…”

Section: Cirft Testingsupporting

confidence: 92%

Sister Rod Destructive Examinations (FY2021)

Montgomery¹,

Bevard²

2022

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This report documents work performed under the Spent Fuel and Waste Disposition's Spent Fuel and Waste Science and Technology program for the US Department of Energy (DOE) Office of Nuclear Energy (NE). This work was performed to fulfill Level 2 Milestone M2SF-22OR010201042, "FY2021 ORNL Report on High Burnup Sibling Pin Testing Results," within work package SF-22OR01020104 and is an update to the work reported in M2SF-21OR010201032, M2SF-19ORO010201026 and M2SF-19OR010201028. Sister Rod Destructive Examinations March 31, 2022 v Planned DE Status / Applicable Appendix Comments Five more tests with unpressurized specimens are expected to be completed in FY22. Tests using pressurized segments are planned to follow the unpressurized tests. DE.01 Measure internal pressure of five baseline and three heattreated rods Complete / Appendix CThe rod internal pressure and the void volume available inside the rod were measured for eight sister rods at room temperature (RT), and all pressures are within the publicly available database envelope. There is a clear correlation between the post-irradiated rod internal pressure and the as-designed fill pressure. The fission gas partial pressure trends well with the rod average burnup. The pressure and void volumes measured are consistent for rods from the same fuel vendor. The product of the partial pressure of the fission gas and the void volume, P f V, is consistent from lab to lab for sister rods from the same assembly, except for the two rods from assembly F35. A comparison of P f V indicates that the ZIRLO-clad rods might have experienced some change in pressure, void volume, or both due to the heat treatment applied, but the M5-clad rods do not exhibit the same effects.Comparisons with predictions from fuel rod performance codes FAST and BISON indicate a tendency for FAST to underpredict pressure and BISON to overpredict pressure.

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“…Averages are provided for burnup, cycles to failure, strain, and flexural rigidity for comparison purposes. The results are consistent with previous data for the same size of fuel rods (17 × 17), as shown in Figure 11, although when trended with stress amplitude, as shown in Figure 12, the sister rod fatigue lifetimes appear to be on the lower side of other lifetime estimates, and some data are below the fatigue limit estimates [14,15].…”

Section: Cirft Testingsupporting

confidence: 92%

Sister Rod Destructive Examinations (FY20)

Montgomery

¹

,

Bevard

²

2020

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This report documents work performed under the Spent Fuel and Waste Disposition's Spent Fuel and Waste Science and Technology program for the US Department of Energy (DOE) Office of Nuclear Energy (NE). This work was performed to fulfill Level 2 Milestone M2SF-21OR010201032, "ORNL High Burnup Confirmatory Demo Sibling Rod Testing Results," within work package SF-21OR01020103 and is an update to the work reported in M2SF-19ORO010201026 and M2SF-19OR010201028. As a part of DOE NE High Burnup Spent Fuel Data Project, Oak Ridge National Laboratory (ORNL) is performing destructive examinations (DEs) of high burnup (HBU) (>45 GWd/MTU) spent nuclear fuel (SNF) rods from the North Anna Nuclear Power Station operated by Dominion Energy. The SNF rods, called sister rods or sibling rods, are all HBU and include four different kinds of fuel rod cladding: standard Zircaloy-4 (Zirc-4), low-tin (LT) Zirc-4, ZIRLO, and M5. The DEs are being conducted to obtain a baseline of the HBU rod's condition before dry storage and are focused on understanding overall SNF rod strength and durability. Composite fuel and defueled cladding will be tested to derive material properties. Although the data generated can be used for multiple purposes, one primary goal for obtaining the post-irradiation examination data and the associated measured mechanical properties is to support SNF dry storage licensing and relicensing activities by (1) addressing identified knowledge gaps and (2) enhancing the technical basis for post-storage transportation, handling, and subsequent disposition. This report documents the status of the ORNL Phase 1 DEs of eight sister rods and outlines the DE tasks performed and the data collected to date, as guided by the sister rod test plans. The DEs are performed using a phased approach, and the Phase 1 DEs being performed at ORNL include: • full-length rod heat treatments (FHT) of three selected sister rods to examine the effects of temperatures reached during dry storage preparation; Sister Rod Destructive Examinations November 30, 2020 v Planned DE Status Comments measurement uncertainty of the baseline rod, and the heat-treatment did not appear to affect the void volume. No conclusions could be made about the effects of the heat-treatment on the Zirc-4-clad rod based on a comparison with the LT Zirc-4 baseline rod or the Pacific Northwest National Laboratory Zirc-4-clad rod. Comparisons with predictions from fuel rod performance codes FAST and BISON indicate a tendency for FAST to overpredict void volume and BISON to underpredict void volume. Measure the transmissibility of gas along the pellet stack Complete Pellet stack gas transmissibility at room temperature was measured by using depressurization tests on eight rods and transmission tests on three rods. In all cases, gas was transmissible through the pellet stack at room temperature, requiring between 30 min and 24 h to reach equilibrium conditions, depending upon the pressure differential applied. The data correlates well using the Muskat-Poiseuille porous media me...

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Modeling Structural Loading of used Nuclear Fuel Under Conditions of Normal Transportation

Cited by 4 publications

References 4 publications

Sister Rod Destructive Examinations (FY22)

Sister Rod Destructive Examinations (FY22)

Sister Rod Destructive Examinations (FY2021)

Sister Rod Destructive Examinations (FY20)

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