CFD Analyses of the TN-24P PWR Spent Fuel Storage Cask

Brewster, Robert; Baglietto, Emilio; Volpenhein, E.C.; Bajwa, Christopher S.

doi:10.1115/pvp2012-78491

Cited by 26 publications

(17 citation statements)

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“…The ambient temperature for the winter conditions is taken to be 283 K (10˚C) and the heat transfer coefficient was calculated accordingly for the air on the radial and top surface of cask, which were found to be 4.26 W/m 2 and 5 W/m 2 , respectively. The emissivity, which is around 0.6 -0.8 in the dry storage system (Brewster et al, 2012;Kim et al, 2014) are the same values used in the previous case for summer conditions. It can be seen from Table 4-9 that in summer less amount of heat is removed by the air as the change in the temperature of the air is lesser in summer when compared to winter.…”

Section: Full-scale Model With Thermal Radiation and Transmissivity =mentioning

confidence: 78%

“…In thermal radiation simulation, the key parameter is the emissivity and the value is around 0.6 -0.8 in the dry storage system simulation (Brewster et al, 2012;Kim et al, 2014). The Kirchhoff's Law requires that for each boundary or interface, the sum of emissivity (α), reflectivity (ρ), and transmissivity (τ) equals unity.…”

Section: Effects Of Transmissivity On Temperature Fieldsmentioning

confidence: 99%

“…Due to high temperatures, radiation mode of heat transfer is also considered in this simulation to obtain a more accurate temperature distribution. The key parameter in thermal radiation simulation is the emissivity, and its value is around 0.6 -0.8 for the dry storage system (Brewster et al, 2012;Kim et al, 2014). It can be seen from Table 4-8 that accounting for radiation as a mode of heat transfer considerably reduces the average canister wall temperature, but increases the outer wall temperature by a small amount.…”

Section: Full-scale Model With Thermal Radiation and Transmissivity (mentioning

confidence: 99%

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Probabilistic Multi-Hazard Assessment of Dry Cask Structures

Bencturk¹,

Padgett²,

Uddin³

2017

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This study is focused on vertical concrete dry casks and their structural performance in seismic and tip-over events, aiming for risk estimation of large seismically induced motions (large sliding and tip-over) and structural damage due to the tip-over loads. Both numerical and experimental work was conducted to investigate the long-term performance of the concrete outerpacks with an exposed surface. Material level studies provided additional data to the existing literature on how to accelerate the corrosion and alkali-silica reactivity (ASR) in concrete without altering the key properties of the material to observe significant levels of deterioration in a short period of time. The developed methods are specifically geared towards large-scale applications of structural systems. Detailed thermal analysis was performed to determine the temperature distributions in both prototype and scaled casks. Tip-over experiments were performed on both intact and aged physical models of concrete casks to compare the structural performance in terms under combined aging and mechanical loading. The influence of shrinkage, creep and gravity loading in the long-term and combined ASR and tip-over impact were investigated using detailed numerical simulations. In the probabilistic assessments, the effect of different sources of aleatory and epistemic uncertainties on the structural performance of the dry casks are studied, and probabilistic models are developed for some of the key structural responses. Fragility curves are developed for seismic sliding motion and tip-over, as well as large acceleration in case of tip-over, and effect of different parameters' variations on the response is studied herein. Probabilistic seismic analysis on a portfolio of vertical concrete dry casks is performed in this study considering common cask configurations in the United States. Probabilistic seismic demand models for the maximum sliding distance and maximum angle of rotation of the casks are developed, and seismic fragility analysis and parameter study are performed. Seismic risk of large sliding motions and tip-over is estimated. In addition, finite element models are developed to analyze the structural response of a dry cask to impact tip-over loads considering the influence of material and structural parameter variations. Impact fragility curves are developed for the mean maximum acceleration of the cask in tip-over events, and effect of geometric and material properties on the response is investigated. 2 2 Volume V 3 3 Mass M 3 3 2.5. REFERENCES

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Section: Full-scale Model With Thermal Radiation and Transmissivity =mentioning

confidence: 78%

Section: Effects Of Transmissivity On Temperature Fieldsmentioning

confidence: 99%

Section: Full-scale Model With Thermal Radiation and Transmissivity (mentioning

confidence: 99%

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Probabilistic Multi-Hazard Assessment of Dry Cask Structures

Bencturk¹,

Padgett²,

Uddin³

2017

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“…There is interest again to the thermal analysis of non-ventilated metal casks mainly because the experimental tests data becomes available. S. H. Yoo et al [14], R. A. Brewster et al [15] performed detailed modelling using Fluent code down to the fuel rods to compare within the effective thermal conductivity and porous media approximation for fuel assemblies but for a small scale models.…”

Section: Introductionmentioning

confidence: 99%

Modeling of decay heat removal from CONSTOR RBMK-1500 casks during long-term storage of spent nuclear fuel

Poškas

Šimonis

Jouhara

et al. 2019

Energy

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Management of spent nuclear fuel is a very important part in the whole cycle of nuclear energy generation. Ignalina nuclear power plant operated two RBMK-1500 reactors that are now being decommissioned. After careful consideration "dry" storage technology in casks was selected for the interim storage of spent nuclear fuel (SNF) for up to 50 years. SNF after pre-storage time in water pools for not less than 5 years is loaded into cast-iron or metal-concrete casks. In this paper decay heat removal was modeled from specific GNB (Gesellschaft für Nuklear Behälter GmbH) metalconcrete (CONSTOR RBMK-1500) casks for the long-term storage period up to 300 years. The ALGOR code was used for the numerical modeling of the distribution of the heat fluxes and temperatures in a loaded cask placed in an open type storage facility in both summer and winter taking into account local environmental conditions. A local sensitivity analysis of the impact of fuel parameter uncertainties is also performed.

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“…In some models, the fuel and basket are replaced by a smeared region with an effective thermal conductivity and an effective porosity. Other models use an accurate-geometry computational domain where the fuel rods, gas and the baskets are distinctly modeled [18][19][20][21]. These models are used to predict the peak cladding temperature for a range of fuel heat generation rates.…”

Section: Introductionmentioning

confidence: 99%

Effects of Gas Rarefaction on Used Nuclear Fuel Cladding Temperatures during Vacuum Drying

Hadj-Nacer¹,

Manzo²,

et al. 2016

Nuclear Technology

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A two-dimensional computational model of a loaded used nuclear fuel canister filled with dry helium gas was constructed to predict the cladding temperature during vacuum drying conditions. The model includes distinct regions for the fuel pellets, cladding and helium within each basket opening, and it calculates conduction heat transfer within all solid components, heat generation within the fuel pellets, and conduction and surface-to-surface radiation across the gas-filled regions. First steady-state simulations are performed to determine peak clad temperatures as a function of fuel heat generation rate, assuming the canister is filled with atmospheric-pressure helium. The allowable fuel heat generation rate, which brings the peak clad temperature to its limit is evaluated. The discrete-velocity-method is then used to calculate slip-regime rarefied-gas conduction across planar and cylindrical helium-filled gaps. These results are used to verify the Lin-Willis solid/gas interface thermal-resistance model for a range of thermal accommodation coefficients, α. The Lin-Willis model is then implemented at the solid/gas interfaces within the canister model. Finally, canister simulations with helium pressures of 100 and 400 Pa and α = 1, 0.4 and 0.2 are performed to determine how much hotter the fuel cladding is under vacuum drying conditions compared to atmospheric pressure. For α = 0.4, the fuel heat generation rates that bring the clad temperature to its allowed limit for helium pressures of 400 and 100 Pa are reduced by 10% and 25%, respectively compared to atmospheric-pressure conditions. Transient simulations show that the cladding reaches it steady state temperatures roughly 20 to 30 hours after water is removed from the canister.

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CFD Analyses of the TN-24P PWR Spent Fuel Storage Cask

Cited by 26 publications

References 0 publications

Probabilistic Multi-Hazard Assessment of Dry Cask Structures

Probabilistic Multi-Hazard Assessment of Dry Cask Structures

Modeling of decay heat removal from CONSTOR RBMK-1500 casks during long-term storage of spent nuclear fuel

Effects of Gas Rarefaction on Used Nuclear Fuel Cladding Temperatures during Vacuum Drying

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