The Effects of Creep and Hydride on Spent Fuel Integrity During Interim Dry Storage

Kim, Hyun Gil; Jeong, Yong Hwan; Kim, Kyu Tae

doi:10.5516/net.2010.42.3.249

Cited by 25 publications

(12 citation statements)

References 7 publications

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“…Results are shown for the Continuum model (atmospheric pressure) and moderatelyrarefied model with pressure P=500 Pa and two thermal accommodation coefficient values α=1 and 0.4, and two values of the LJ molecular diameter d=1.9 Å and 2.33 Å. In the figure also two maximum allowable cladding temperatures that cause the radial hydride formation are drawn by horizontal lines at T=370°C [12] and 400°C [6].…”

Section: Results and Disscussionmentioning

confidence: 99%

“…Until further guidance is developed, high burnup fuel will be handled on a case-by-case basis [6]. In other countries like Germany the maximum cladding temperature is 370°C [12] for both storage and drying operations.…”

Section: Introductionmentioning

confidence: 99%

“…Simulations are performed using a continuum model for a helium pressure of 1 atm (10 5 Pa), and a rarefied gas model for the helium at 500 Pa. The fuel heat generation rates that bring the cladding temperature to ISG-11 limit temperature of 400°C, and a reduced limit of 370°C used in Germany [12], are reported.…”

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Prediction of Cladding Temperatures Within a Used Nuclear Fuel Transfer Cask Filled With Rarefied Helium

Manzo

Green

Nacer

et al. 2014

Volume 7: Operations, Applications and Components

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During the used nuclear fuel vacuum drying process, helium is evacuated to pressures as low as 70 Pa, to promote water vaporization and removal. At these low pressures the gas is rarefied to the extent that there is a temperature jump thermal resistance between the surface and gas. This occurs when the mean free path of a molecule becomes a comparable to the characteristic length of a system. In order to correctly apply this jump model to a nuclear transfer cask, a two dimensional model of parallel plates and concentric cylinders were created using ANSYS/Fluent package. Heat generation was plotted against a variety of relevant pressures. The results in these simple geometries are compared to kinetic model calculations, performed by other investigators, to determine the appropriate collision diameters to use in rarefied helium gas simulations within complex geometries. A two dimensional mesh of a transfer cask containing 24 pressurized water reactor used fuel assemblies is then constructed, and the rarefied gas model was implemented in the helium-filled regions between the fuel and basket support structures. Steady state simulations with a fuel heat generation rate of 710 W/m/assemble shows that the cladding is measurably hotter when the helium gas pressure is reduced from atmospheric conditions ∼105 Pa to 500 Pa. The heat generation rate that brings the peak cladding temperature to a hydride dissolution temperature of 400°C is as much as 10% lower when the gas is at 500 Pa than under atmospheric conditions.

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Section: Results and Disscussionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Prediction of Cladding Temperatures Within a Used Nuclear Fuel Transfer Cask Filled With Rarefied Helium

Manzo

Green

Nacer

et al. 2014

Volume 7: Operations, Applications and Components

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show abstract

“…4a, for the 2D model with the same conditions used in that figure. The maximum temperature or peak clad temperature obtained for the 2D model is TPC=336°C, which is lower than the temperature of radial hydride formation considered in the US, TRH=400°C [4], or the reduced temperature considered in Germany, TRH,R=370°C [30]. The peak temperature of the inner assembly are ~37°C hotter than that of the outer assembly through which the r-axis passes.…”

Section: Resultsmentioning

confidence: 73%

Geometrically-Accurate-Three-Dimensional Simulations of a Used Nuclear Fuel Canister Filled With Helium

Manzo

Nacer

Greiner

2015

Volume 7: Operations, Applications and Components

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This paper presents preliminary results of heat transfer simulations performed in geometrically-accurate-three-dimensional model of nuclear fuel canister filled with helium. The numerical model represents a vertical canister, which relies on natural convection as its primary heat transfer mechanism, containing 24 PWR fuel assemblies. The model includes distinct regions for the fuel pellets, cladding and gas regions within each basket opening. Symmetry boundary conditions are employed so that only one-eighth of the package cross-section is included. The canister is assumed to be filled with helium at atmospheric pressure. A constant temperature of 101.7°C is employed on the canister outer surfaces, assuming the canister to be surrounded with water. These conditions of pressure and temperature were considered, in this paper, for comparison purpose with previous work. The effects of buoyancy-induced gas motion and natural convection, along with radiation and conduction through gas regions and solid are considered. Steady state simulations using ANSYS/Fluent were performed for different heat generation rates in the fuel regions. Simulations that include the effect of natural convection and others that do not include this effect are conducted. The peak cladding temperature and its radial and axial locations are reported. The maximum allowable heat generation that brings the cladding temperatures to the radial hydride formation limit (TRH=400°C) is also reported. The results of the three dimensional model simulations were compared to two dimensional model simulations for the same heat generation rate. The results showed that the two-dimensional simulations overestimate the temperature in the canister by almost 70°C.

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“…Hence, the primary aim of ENIGMA analysis is to predict whether or not the cladding could fail via these mechanisms. This is done by comparing the clad hoop stresses, clad creep hoop strains and clad temperatures that are predicted during the post-irradiation operations to safety limits, typically 90 or 120 MPa, 1%, and 370 to 570°C, respectively [24]. (Thus, radial hydride formation is not modelled explicitly -instead the clad hoop stress is shown to be maintained below a safety limit which precludes the formation of radial hydrides.…”

Section: Development Of Enigma For Dry Storage Assessmentsmentioning

confidence: 99%

Development of the Enigma Fuel Performance Code for Whole Core Analysis and Dry Storage Assessments

Rossiter¹

2011

Nuclear Engineering and Technology

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The Effects of Creep and Hydride on Spent Fuel Integrity During Interim Dry Storage

Cited by 25 publications

References 7 publications

Prediction of Cladding Temperatures Within a Used Nuclear Fuel Transfer Cask Filled With Rarefied Helium

Prediction of Cladding Temperatures Within a Used Nuclear Fuel Transfer Cask Filled With Rarefied Helium

Geometrically-Accurate-Three-Dimensional Simulations of a Used Nuclear Fuel Canister Filled With Helium

Development of the Enigma Fuel Performance Code for Whole Core Analysis and Dry Storage Assessments

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