Corrosion by Fused Salts and Heavy Liquid Metals—A Survey

Shimotake, H.; Hesson, J.C.

doi:10.1021/ba-1967-0064.ch012

Cited by 13 publications

(11 citation statements)

References 0 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The activity coefficients of some actinides (U, Th, Np, Pu, Am) and fission products (Y, La, Ce, Pr, Nd, Sm, Eu, Gd, Tb, Dy, and Er) were recently summarized by Zhang et al and the relationship between solubility and activity coefficient of a metal in liquid Bi is also given in the reference. The correlations between solubility and temperature for elements Be, Mg, Ca, Sr, Ba, Al, Si, Ce, Lu, Th, Ti, Zr, Hf, V, Cb, Ta, Cr, Mo, W, Mn, Fe, Ru, Os, Co, Rh, Ni, Pd, and Pt were summarized in previous studies . When the solubility is low, the solution can be an infinite dilution, and the activity coefficient is non‐concentration dependent and it can be calculated using the correlation between solubility and activity coefficient that is given by Zhang et al Recently, the concentration‐dependent activity coefficients of Dy, Gd, Ho, La, Lu, Nd, Tb, and Tm were calculated based on CALPHAD .…”

Section: On‐line Purification Methodsmentioning

confidence: 99%

“…The correlations between solubility and temperature for elements Be, Mg, Ca, Sr, Ba, Al, Si, Ce, Lu, Th, Ti, Zr, Hf, V, Cb, Ta, Cr, Mo, W, Mn, Fe, Ru, Os, Co, Rh, Ni, Pd, and Pt were summarized in previous studies. [64,65] When the solubility is low, the solution can be an infinite dilution, and the activity coefficient is non-concentration dependent and it can be calculated using the correlation between solubility and activity coefficient that is given by Zhang et al [63] Recently, the concentration-dependent activity coefficients of Dy, Gd, Ho, La, Lu, Nd, Tb, and Tm were calculated based on CALPHAD. [66] The Bi-fission-product binary or ternary system were also investigated experimentally or theoretically using thermodynamic analysis.…”

Section: Bi-li/salt Extractionmentioning

confidence: 99%

See 1 more Smart Citation

Impurities in Primary Coolant Salt of FHRs: Chemistry, Impact, and Removal Methods

Zhang

2019

Energy Tech

View full text Add to dashboard Cite

The fluoride salt‐cooled high‐temperature reactor (FHR) is one of the Gen. IV reactor concepts. Considering the complexity of salt chemistry, radiation risk, impurity‐induced material corrosion, and impurity‐induced solid precipitation, the salt chemistry should be well controlled. Therefore, molten salt cleanup systems are needed in operation. Based on the experience of molten salt reactors (MSRs) and available data, the present study identifies the types of impurities, their potential sources, and their impact in FHR primary coolants. Cleanup methods for each type of impurity and future research activities are also discussed.

show abstract

Section: On‐line Purification Methodsmentioning

confidence: 99%

Section: Bi-li/salt Extractionmentioning

confidence: 99%

Impurities in Primary Coolant Salt of FHRs: Chemistry, Impact, and Removal Methods

Zhang

2019

Energy Tech

View full text Add to dashboard Cite

show abstract

“…Therefore removal of moisture from the chloride melts would be desirable; however, it is usually very difficult. 40 The compilation by MacKenzie 32 indicates that stainless steel may be acceptable as a container material for NaCl at 1830°F (1000°C) based on short-term experiments. Janz and co-workers 17 made a similar observation for the KCl-LiCl eutectic mixture.…”

Section: Corrosion By Fluoridesmentioning

confidence: 99%

Molten salt thermal energy storage systems: salt selection

Maru¹,

Dullea²,

Huang³

1976

View full text Add to dashboard Cite

A research program aimed at the development of a molten salt thermal energy storage system commenced in June 1976. This topical report describes work performed under Task I: Salt Selection. A total of 31 inorganic salts and salt mixtures, including 9 alkali and alkaline earth carbonate mixtures, were evaluated for their suitability as heat-of-fusion thermal energy storage materials at temperatures of 850 °F to 1000°F. Thermo physical properties, safety hazards, corrosion, and cost of these salts were compared on a common basis. We concluded that because alkali carbonate mixtures show high thermal conductivity, low volumetric expansion onmelting, low corrosivity and good stability, they are attractive as heat-of-fusion storage materials in this temperature range. A 35 weight percent Li 2 C0 3-65 weight percent K 2 C0 3 (50 mole percent Li 2 CC>3-50 mole percent K 2 COj) mixture was selected as a model system for further experimental work. This is a eutectoid mixture having a heat of fusion of 148 Btu/lb (82 cal/g) that forms an equimolar compound, LiKCC^. The Li 2 C0 3-K 2 C03 mixture is intended to serve as a model system to define heat transfer characteristics,potential problems, and to provide "first-cut" engineering data required for the prototype system. The cost of a thermal energy storage system containing this mixture cannot be predicted until system characteristics are better defined. However, our comparison of different salts indicated that alkali and alkaline earth chlorides may be more attractive from a salt cost point of view. The long-.terrn corrosion characteristics and the effects of volume change on melting for the chlorides should be investigated to determine their overall suitability as a heat-of-fusion storage medium.

show abstract

“…During the past year, chemical studies in support of the salt transport purification and separations of plutonium and uranium have been conducted. Solubility measurements were obtained for the following liquid alloy systems: (1) plutonium, uranium, zirconium, cerium, niobium, and molybdenum in Cu-Mg alloys that were being considered as donor alloys, (2) plutonium and uranium in Zn-Mg alloys that were being considered als acceptor alloys, and (3) plutoniuni, uranium, and cerium in Mg-Zn-Cd alloys that were also being considered as acceptor alloys. Distribution coefficients were determined for the following liquid metal-molten salt systems:…”

Section: Chemistry Of Salt Transport Separationsmentioning

confidence: 99%

“…Recently completed experiments on the engineering development of salt transport separations have been of an exploratory nature and have had the following objectives: (1) to demonstrate the engineering feasibility of salt transport separations, (2) to provide a basis for the further development of equipment and techniques, and (3) to determine the fission product decontamination obtainable by this method.…”

Section: Engineering Studies Of Salt Transport Separationsmentioning

confidence: 99%

Chemical Engineering Division Research Highlights, May 1966--April 1967.

1967

View full text Add to dashboard Cite

show abstract

Corrosion by Fused Salts and Heavy Liquid Metals—A Survey

Cited by 13 publications

References 0 publications

Impurities in Primary Coolant Salt of FHRs: Chemistry, Impact, and Removal Methods

Impurities in Primary Coolant Salt of FHRs: Chemistry, Impact, and Removal Methods

Molten salt thermal energy storage systems: salt selection

Chemical Engineering Division Research Highlights, May 1966--April 1967.

Contact Info

Product

Resources

About