scholarly journals PRODUCTION OF REACTOR FUEL OXIDES FROM MOLTEN CHLORIDE SALT SOLUTIONS

1963 ◽  
Author(s):  
G E Benedict ◽  
K M Harmon ◽  
G Jr Jansen ◽  
L K Mudge ◽  
F A Scott
Keyword(s):  
Reactor Fuel ◽  
Chloride Salt ◽  
Salt Solutions ◽  
Molten Chloride

Application of In Situ X-ray Absorption Spectroscopy to Study Dilute Chromium Ions in a Molten Chloride Salt

2019 ◽  
Author(s):  
Jisue Moon ◽  
Carter Abney ◽  
Dmitriy Dolzhnikov ◽  
James M. Kurley ◽  
Kevin A. Beyer ◽  
...  
Keyword(s):  
Absorption Spectroscopy ◽  
Local Structure ◽  
Chloride Salt ◽  
X Ray ◽  
Molten Chloride ◽  
Stable Species ◽  
Higher Temperature ◽  
Cr Concentration ◽  
X Ray Absorption

The local structure of dilute CrCl<sub>3</sub> in a molten MgCl<sub>2</sub>:KCl salt was investigated by <i>in situ</i> x-ray absorption spectroscopy (XAS) at temperatures from room temperature to 800<sup>o</sup>C. This constitutes the first experiment where dilute Cr speciation is explored in a molten chloride salt, ostensibly due to the compounding challenges arising from a low Cr concentration in a matrix of heavy absorbers at extreme temperatures. CrCl<sub>3</sub> was confirmed to be the stable species between 200 and 500<sup>o</sup>C, while mobility of metal ions at higher temperature (>700<sup>o</sup>C) prevented confirmation of the local structure.

scholarly journals Thermal and Transport Properties of Molten Chloride Salts with Polarization Effect on Microstructure

Energies ◽  
2021 ◽  
Vol 14 (3) ◽  
pp. 746
Author(s):  
Jianfeng Lu ◽  
Senfeng Yang ◽  
Gechuanqi Pan ◽  
Jing Ding ◽  
Shule Liu ◽  
...  
Keyword(s):  
Heat Capacity ◽  
Polarization Effect ◽  
Chloride Salt ◽  
Coulombic Interaction ◽  
Molten Chloride ◽  
Self Diffusion ◽  
Local Structures ◽  
Property Data ◽  
Chloride Salts ◽  
And Storage

Molten chloride salt is recognized as a promising heat transfer and storage medium in concentrating solar power in recent years, but there is a serious lack for thermal property data of molten chloride salts. In this work, local structures and thermal properties for molten chloride salt—including NaCl, MgCl2, and ZnCl2—were precisely simulated by Born–Mayer–Huggins (BMH) potential in a rigid ion model (RIM) and a polarizable ion model (PIM). Compared with experimental data, distances between cations, densities, and heat capacities of molten chloride slats calculated from PIM agree remarkably better than those from RIM. The polarization effect brings an extra contribution to screen large repulsive Coulombic interaction of cation–cation, and then it makes shorter distance between cations, larger density and lower heat capacity. For NaCl, MgCl2, and ZnCl2, PIM simulation deviations of distances between cations are respectively 3.8%, 3.7%, and 0.3%. The deviations of density and heat capacity for NaCl between PIM simulation and experiments are only 0.6% and 2.2%, and those for MgCl2 and ZnCl2 are 0.7–10.7%. As the temperature rises, the distance between cations increases and the structure turns into loose state, so the density and thermal conductivity decrease, while the ionic self-diffusion coefficient increases, which also agree well with the experimental results.

scholarly journals Neutronic Analysis of LEU-started Molten Chloride Fast Reactor without Fuel Reprocessing

2021 ◽  
Vol 4 (1) ◽  
pp. 8
Author(s):  
R. Andika Putra Dwijayanto ◽  
Andang Widi Harto
Keyword(s):  
Fast Reactor ◽  
Molar Fraction ◽  
Chloride Salt ◽  
Inherent Safety ◽  
Delayed Neutron ◽  
Core Zone ◽  
Molten Chloride ◽  
Enriched Uranium ◽  
Fuel Reprocessing ◽  
Coefficient Of Reactivity

One of the rarely explored molten salt reactor (MSR) designs is the molten chloride fast reactor (MCFR). This MSR design employs chloride salt instead of fluoride and operated in a fast spectrum. MCFR brings all the advantages of an MSR including breeding whilst being able to burn plutonium and minor actinides efficiently. Since not many countries have access to civilian plutonium, MCFR can also be started using low-enriched uranium (LEU). This study is an initial neutronic analysis of an MCFR using LEU as its startup fuel. Parameters analyzed are conversion ratio (CR) and its neutronic safety, namely effective delayed neutron fraction (βeff), temperature coefficient of reactivity (TCR), and void coefficient of reactivity (VCR). The core is divided into Core Zone and Blanket Zone. The fuel composition of NaCl-UCl3 with a molar fraction ratio of 60:40 and 50:50 is used in Core Zone and Blanket Zone, respectively. The neutronic calculation is performed using MCNP6 code with ENDF/B-VII library. For reference geometry, CR is valued at 0.9298, βeff at 0.00731, TCR at -19.8 pcm/°C, and average VCR at -154.31 pcm/void%. Thereby, the MCFR fulfills inherent safety criteria. Although its value is remarkably high, CR can be further optimized by modifying the separator and reflector material.

Measurement of Molten Chloride Salt Flow and Demonstration of Simulated Fission Product Removal Using a Zeolite Column Apparatus for Spent Salt Treatment in Pyroprocessing

2014 ◽  
Vol 188 (1) ◽  
pp. 83-96 ◽  
Author(s):  
Koichi Uozumi ◽  
Takatoshi Hijikata ◽  
Takeshi Tsukada ◽  
Tadafumi Koyama ◽  
Takayuki Terai ◽  
...  
Keyword(s):  
Fission Product ◽  
Chloride Salt ◽  
Salt Treatment ◽  
Molten Chloride ◽  
Column Apparatus ◽  
Product Removal ◽  
Salt Flow

Chlorine Production by HCl Oxidation in a Molten Chloride Salt Catalyst

2018 ◽  
Vol 57 (23) ◽  
pp. 7795-7801 ◽  
Author(s):  
Shizhao Su ◽  
Davide Mannini ◽  
Horia Metiu ◽  
Michael J. Gordon ◽  
Eric W. McFarland
Keyword(s):  
Chloride Salt ◽  
Molten Chloride

scholarly journals Preparation of uranium(III) in a molten chloride salt: a redox mechanistic study

2018 ◽  
Vol 317 (2) ◽  
pp. 925-932 ◽  
Author(s):  
Hugues Lambert ◽  
Timothy Kerry ◽  
Clint A. Sharrad
Keyword(s):  
Mechanistic Study ◽  
Chloride Salt ◽  
Molten Chloride

Thermodynamics of reductive extraction of actinides and lanthanides from molten chloride salt into liquid metal

1998 ◽  
Vol 271-273 ◽  
pp. 587-591 ◽  
Author(s):  
H. Moriyama ◽  
H. Yamana ◽  
S. Nishikawa ◽  
S. Shibata ◽  
N. Wakayama ◽  
...  
Keyword(s):  
Liquid Metal ◽  
Chloride Salt ◽  
Molten Chloride
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