FRAPCON analysis of cladding performance during dry storage operations

Richmond, David; Geelhood, Kenneth J.

doi:10.1016/j.net.2018.01.003

Cited by 12 publications

(3 citation statements)

References 4 publications

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“…For that, considering the oxidizing effect of water vapour [21], the H 2 capacity to prevent oxidation of uranium to high oxidation state (VI) [36] and that oxidation is a temperature dependent reaction, several temperatures (60 • C, 200 • C and 350 • C) with water vapour/hydrogen were tested. The temperature values studied were below the maximum allowable of 400 • C of dry storage, required to preserve the fuel rod cladding [37]. Fig.…”

Section: Porous Samplesmentioning

confidence: 88%

X-Ray Photoelectron Spectroscopy (Xps) Study of Surface Oxidation of Uo2 Doped with Gd2o3 at Different Temperatures and Atmospheres

García-Gómez¹,

Giménez²,

Casas³

et al. 2023

Preprint

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Section: Porous Samplesmentioning

confidence: 88%

X-Ray Photoelectron Spectroscopy (Xps) Study of Surface Oxidation of Uo2 Doped with Gd2o3 at Different Temperatures and Atmospheres

García-Gómez¹,

Giménez²,

Casas³

et al. 2023

Preprint

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“…Quite recently, NRC sponsored the Pacific Northwest National Laboratory to perform FRAPCON calculations under drying and storage conditions for boiling water reactor, standard PWR, and IFBA PWR fuel rods using a validated model for gas release from the B-10-containing absorber on the outer surface of the fuel pellets for IFBA fuel rods [22]. For standard PWR fuel rods, the peak hoop stress occurred during storage and was bounded by 53 MPa.…”

Section: Relevant Ranges Of Internal Pressures and Hoop Stressesmentioning

confidence: 99%

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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“…Other conditions impacting on the formation of U 3 O 8 have been studied under the circumstances expected during dry storage of the fuel, especially focused on temperature. At the interim storage facilities, the upper limit temperature allowed in inert atmosphere for LWR fuel is 400 °C 9 , 11 , 17 , to protect the fuel rod cladding 18 . During normal conditions of storage, there will be a range of temperatures lower than the maximum allowable of 400 °C.…”

Section: Introductionmentioning

confidence: 99%

Exploring the impact of temperature and oxygen partial pressure on the spent nuclear fuel oxidation during its dry management

Milena-Pérez

Bonales

Rodríguez-Villagra

et al. 2023

Sci Rep

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The management of Spent Nuclear Fuel (SNF) comprises different stages in which security is demonstrated. Nevertheless, fundamental research can lead to other design options that must be considered. Currently, one of the focuses is the dry interim storage option, as the shortest-term solution until final repositories are available. During this stage, one concern is the oxidation of the fuel. If UO2 (SNF matrix) is exposed to air at high-enough temperature, formation of U3O8 takes place. The larger volume of this phase could entail stresses on the SNF clad, which is the first barrier to prevent radioactive material release. It is known that this oxidation is a temperature-dependent reaction and ensuring an inert atmosphere discards any effect during SNF dry management. However, at what extent temperature and oxygen concentration would have an impact on the U3O8 formation is not established, being the available experimental data very scarce. We follow this oxidation in representative ranges of temperature and oxygen concentration of dry storage facilities by using in-situ Raman spectroscopy. The results show that temperature is a more-affecting factor than the oxygen concentration at the studied conditions. Therefore, efforts to limit temperatures would yield more benefits in preserving fuel matrix integrity.

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FRAPCON analysis of cladding performance during dry storage operations

Cited by 12 publications

References 4 publications

X-Ray Photoelectron Spectroscopy (Xps) Study of Surface Oxidation of Uo2 Doped with Gd2o3 at Different Temperatures and Atmospheres

X-Ray Photoelectron Spectroscopy (Xps) Study of Surface Oxidation of Uo2 Doped with Gd2o3 at Different Temperatures and Atmospheres

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

Exploring the impact of temperature and oxygen partial pressure on the spent nuclear fuel oxidation during its dry management

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