Enthalpies and Heat Capacities of Solid and Molten Fluoride Mixtures

Powers, W.D.; Blalock, Glenn

doi:10.2172/4794927

Cited by 13 publications

(9 citation statements)

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“…The results of drop calorimetry performed at ORNL using an ice calorimeter exhibited unquantified but significant scatter leading the researchers to conclude that only a linear fit of the measured enthalpy data with respect to temperature was justified, meaning a the liquid-state heat capacity value was constant with temperature. They calculated the heat capacity of eutectic liquid FLiNaK to be 1.88 J g -1 K -1 , which was within 10% of other reported values using drop calorimetry across a multi-lab study [6].…”

Section: Heat Capacity Of Flinaksupporting

confidence: 73%

Thermochemical Property Measurements of FLiNaK and FLiBe in FY 2020

T.¹,

Rose²,

Krueger³

et al. 2022

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is a U.S. Department of Energy laboratory managed by UChicago Argonne, LLC under contract DE-AC02-06CH11357. The Laboratory's main facility is outside Chicago, at 9700 South Cass Avenue, Argonne, Illinois 60439. For information about Argonne and its pioneering science and technology programs, see www.anl.gov. DOCUMENT AVAILABILITYOnline Access: U.S. Department of Energy (DOE) reports produced after 1991 and a growing number of pre-1991 documents are available free at OSTI.GOV (http://www.osti.gov/), a service of the US Dept. of Energy's Office of Scientific and Technical Information.

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Section: Heat Capacity Of Flinaksupporting

confidence: 73%

Thermochemical Property Measurements of FLiNaK and FLiBe in FY 2020

T.¹,

Rose²,

Krueger³

et al. 2022

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“…The units were reported in cal g -1 and not J g -1 , which led to the FY21 calculations using an incorrect value of 1661 J g -1 . The correct heat of fusion of FLiNaK is 399 J g -1 , which was originally reported in Powers and Blalock (1956).…”

Section: Summary Of Fy21 Spreading and Heat Transfer Results Using Co...mentioning

confidence: 63%

Modeling Molten Salt Spreading and Heat Transfer using MELTSPREAD – Model Development Updates

Thomas¹,

Jackson²,

Farmer³

2022

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is a U.S. Department of Energy laboratory managed by UChicago Argonne, LLC under contract DE-AC02-06CH11357. The Laboratory's main facility is outside Chicago, at 9700 South Cass Avenue, Argonne, Illinois 60439. For information about Argonne and its pioneering science and technology programs, see www.anl.gov. DOCUMENT AVAILABILITY Online Access: U.S. Department of Energy (DOE) reports produced after 1991 and a growing number of pre-1991 documents are available free at OSTI.GOV (http://www.osti.gov/), a service of the US Dept. of Energy's Office of Scientific and Technical Information.

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“…The heat capacity of nafzirf has been reviewed for both solid and liquid temperatures. • C with a 10-15% uncertainty [35,124]. All values were originally reported in units of cal-g/K and were converted using the conversion factor is 4.187 J/kg-K per cal/g-K .…”

Section: Densitymentioning

confidence: 99%

“…where ρ is density in kg/m 3 amd T is temperature in Kelvin. and Oak Ridge National Lab (ORNL) [124]. Additional data for various temperatures is presented from correlations presented by Khokhlov [94], Rogers [131], and Williams [162] as…”

Section: Densitymentioning

confidence: 99%

Fluoride-Salt-Cooled High-Temperature Test Reactor Thermal-Hydraulic Licensing and Uncertainty Propagation Analysis

2019

Nuclear Technology

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An important Fluoride-salt-cooled High-temperature Reactor (FHR) development step is to design, build, and operate a test reactor. Through a literature review, liquid-salt coolant thermophysical properties have been recommended along with their uncertainties of 2-20%. This study tackles determining the effects of these high uncertainties by proposing a newly developed methodology to incorporate uncertainty propagation in a thermalhydraulic safety analysis for test reactor licensing. A hot channel model, Monte Carlo statistical sampling uncertainty propagation, and limiting safety systems settings (LSSS) approach are uniquely combined to ensure sufficient margin to fuel and material thermal limits during steady-state operation and to incorporate margin for high uncertainty inputs. The method calculates LSSS parameters to define safe operation. The methodology has been applied to two test reactors currently considered, the Chinese TMSR-SF1 pebble bed design and MIT's Transportable FHR prismatic core design; two candidate coolants, flibe (LiF-BeF 2) and nafzirf (NaF-ZrF 4); and forced flow and natural circulation conditions to compare operating regions and LSSS power (maximum power not exceeding any thermal limits). The calculated operating region accounts for uncertainty (2σ) with LSSS power (MW) for forced flow of 25.37±0.72, 22.56±1.15, 21.28±1.48, and 11.32±1.35 for pebble flibe, pebble nafzirf, prismatic flibe, and prismatic nafzirf, respectively. The pebble bed has superior heat transfer with an operating region reduced ∼10% less when switching coolants and ∼50% smaller uncertainty than the prismatic. The maximum fuel temperature constrains the pebble bed while the maximum coolant temperature constrains the prismatic due to different dominant heat transfer modes. Sensitivity analysis revealed 1) thermal conductivity and thus conductive heat transfer dominates in the prismatic design while convection is superior in the pebble bed, and 2) the impact of thermophysical property uncertainties are ranked in the following order: thermal conductivity, heat capacity, density, and lastly viscosity. Broadly, the methodology developed incorporates uncertainty propagation that can be used to evaluate parametric uncertainties to satisfy guidelines for non-power reactor licensing applications, and method application shows the pebble bed is more attractive for thermal-hydraulic safety. Although the method was developed and evaluated for coolant property uncertainties for FHR, it is readily applicable for any parameters of interest.

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Enthalpies and Heat Capacities of Solid and Molten Fluoride Mixtures

Cited by 13 publications

References 0 publications

Thermochemical Property Measurements of FLiNaK and FLiBe in FY 2020

Thermochemical Property Measurements of FLiNaK and FLiBe in FY 2020

Modeling Molten Salt Spreading and Heat Transfer using MELTSPREAD – Model Development Updates

Fluoride-Salt-Cooled High-Temperature Test Reactor Thermal-Hydraulic Licensing and Uncertainty Propagation Analysis

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