Cladding stress during extended storage of high burnup spent nuclear fuel

Raynaud, Patrick; Einziger, R.E.

doi:10.1016/j.jnucmat.2015.05.008

Cited by 27 publications

(10 citation statements)

References 14 publications

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“…As shown in Section 1.1.1, the PCT of sections of rods that were hot enough to support sufficient radial hydride formation, assuming a high enough hoop stress, will be above 100°C for at least 100 years. Similary, Raynaud and Einziger (2015) estimated that it takes 300 years for cladding temperatures that were at 400°C to decrease to 100°C. The MCT, as shown previously in Table 1, is expected to be approximately 50°C at 300 years.…”

Section: Radial Hydride Testsmentioning

confidence: 99%

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EPRI/DOE High Burnup Fuel Sister Pin Test Plan Simplification and Visualization

Sorenson

Hanson

et al. 2017

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The EPRI/DOE High Burnup Confirmatory Data Project (herein called the "Demo") is a multi-year, multi-entity confirmation demonstration test with the purpose of providing quantitative and qualitative data to show how high-burnup fuel ages in dry storage over a ten-year period. The Demo involves obtaining 32 assemblies of highburnup PWR fuel of four common cladding alloys from the North Anna Nuclear Power Plant, drying them according to standard plant procedures, and then storing them in an NRC-licensed TN-32B cask on the North Anna dry storage pad for ten years. After the ten-year storage time, the cask will be opened and the rods will be examined for signs of aging.

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Section: Radial Hydride Testsmentioning

confidence: 99%

“…Billone and Burtseva (2016) also found that the DBTT for ZIRLO ® is highly sensitive to the hoop stress in the range 90±3 MPa. Raynaud and Einziger (2015) recently performed an analysis of cladding stress during extended storage of HBU SNF. In their analysis, they assumed a burnup of 65 GWd/MTU for a typical 17×17 PWR cladding.…”

Section: Hoop Stressmentioning

confidence: 99%

EPRI/DOE High Burnup Fuel Sister Pin Test Plan Simplification and Visualization

Sorenson

Hanson

et al. 2017

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“…Second, helium produced by α decays of actinides during operation and storage can also be released to the rod free volume and contribute to RIP. Moreover, α-decay damage results in the lattice parameter increase which is associated with fuel swelling [27,28] . Heliuminduced fuel swelling can have important consequences in terms of the Pellet-Cladding Mechanical Interaction (PCMI).…”

Section: Important Phenomenamentioning

confidence: 99%

“…Those interactions generate cascades of displacements resulting in lattice swelling. The literature regarding this phenomenon has been reviewed by Raynaud and Einziger [28] .…”

Section: Fuel Pellet Swellingmentioning

confidence: 99%

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Spent nuclear fuel in dry storage conditions – current trends in fuel performance modeling

Konarski

Cozzo

Khvostov

et al. 2021

Journal of Nuclear Materials

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The role of dry storage in spent nuclear fuel management becomes more and more important. Originally intended to serve as a temporary solution for a few decades until final disposal, now dry storage period is to be extended to 100 years and beyond. It has to be proven for licensing that the fuel rod integrity during dry storage is ensured. Since it is difficult to provide experimental support, the licensing process has to rely largely on numerical simulations. This paper reviews the literature associated with the modeling of spent nuclear fuel under dry storage conditions. The main phenomena threatening the fuel rod integrity and the numerical models representing them are described here. Moreover, the most recent or currently ongoing experimental efforts that could support the modeling of nuclear fuel in dry storage in the future are discussed. Finally, this paper reviews approaches to dry storage modeling chosen by different countries. In general, these approaches are similar and can be described as a calculation chain consisting of neutronics-thermo-hydraulics-fuel performance computations where sensitivity and uncertainty studies are crucial elements.

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Assessing the fracture toughness of Zircaloy-4 fuel rod cladding tubes: impact of delayed hydride cracking

François,

Petit,

Auzoux

et al. 2024

Int J Fract

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Delayed Hydride Cracking (DHC) is a hydrogen embrittlement phenomenon that may potentially occur in Zircaloy-4 fuel claddings during dry storage conditions. An experimental procedure has been developed to measure the toughness of this material in the presence of DHC by allowing crack propagation through the thickness of a fuel cladding. Notched C-ring specimens, charged with 100 wppm of hydrogen, were used and pre-cracked by brittle fracture of a hydrided zone at the notch root at room temperature. The length of the pre-crack was measured on the fracture surface or cross-sections. Additionally, a finite element model was developed to determine the stress intensity factor as a function of the crack length for a given loading. Two types of tests were conducted independently to determine the fracture toughness with and without DHC, K I DHC and K I C , respectively: (i) constant load tests at 150°C, 200°C, and 250°C; (ii) monotonic tests at 25°C, 200°C, and 250°C. The results indicate the following: (1) there is no temperature influence on the DHC toughness of Zircaloy-4 between 150 and 250°C (K I DHC ∈ [7.2; 9.2] MPa √ m), (2) within this temperature range, the fracture toughness of Zircaloy-4 is halved by DHC (K I C ∈ [16.9; 19.7] MPa √ m), (3) the crack propagation rate decreases with decreasing temperature and (4) the time before crack propagation increases as the temperature and loading decrease.

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Cladding stress during extended storage of high burnup spent nuclear fuel

Cited by 27 publications

References 14 publications

EPRI/DOE High Burnup Fuel Sister Pin Test Plan Simplification and Visualization

EPRI/DOE High Burnup Fuel Sister Pin Test Plan Simplification and Visualization

Spent nuclear fuel in dry storage conditions – current trends in fuel performance modeling

Assessing the fracture toughness of Zircaloy-4 fuel rod cladding tubes: impact of delayed hydride cracking

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