High temperature thermodynamic stability study of NaCeF4 in NaF-CeF3 system during waste burning in Molten Salt Reactor

2021 ◽  
pp. 122573
Author(s):  
Sumanta Mukherjee ◽  
Smruti Dash
Keyword(s):  
High Temperature ◽  
Molten Salt ◽  
Thermodynamic Stability ◽  
Stability Study ◽  
Molten Salt Reactor ◽  
Waste Burning

scholarly journals Considerations of Alloy N Code Extension for Commercial Molten Salt Reactor Development and Deployment

2018 ◽  
Author(s):  
Weiju Ren
Keyword(s):  
High Temperature ◽  
Strategic Planning ◽  
Research And Development ◽  
Molten Salt ◽  
Historical Data ◽  
Molten Salt Reactor ◽  
Structural Alloy ◽  
Commercial Development ◽  
Code Extension ◽  
Nuclear Applications

For commercial development and deployment of the molten salt reactor, a structural alloy that provides both strength at high temperature and resistance to very corrosive molten salt environment is required. To meet this requirement, a survey is conducted on domestic and international candidate alloys. Alloy N turns out to be the sole frontrunner in readiness for qualification to enable the desired deployment within an estimated 10 years. A review of the qualification for commercial nuclear applications indicates that Alloy N has met a large portion of the requirements. Gaps in the qualification are also identified. A search for historical data is underway to retrieve information needed for filling the gaps and upgrading the qualification. Scope of the discovered historical data is briefly discussed and strategic planning for research and development pathway is suggested to ensure successful evolution in commercial deployment of the molten salt reactor system.

The Mechanical Interaction of Clad and Base Metal for Molten Salt Reactor Structural Components

2018 ◽  
Author(s):  
M. C. Messner ◽  
V.-T. Phan ◽  
R. I. Jetter ◽  
T.-L. Sham
Keyword(s):  
High Temperature ◽  
Molten Salt ◽  
Mechanical Response ◽  
Base System ◽  
Molten Salt Reactor ◽  
Structural Components ◽  
Mechanical Interaction ◽  
Base Materials ◽  
Creep Fatigue ◽  
Axisymmetric Structures

Cladding structural components with a corrosion resistant material may greatly extend the design life of molten salt reactor concepts. A complete design methodology for such cladded, high temperature nuclear components will require addressing many issues: fabrication, corrosion resistance, metallurgical interaction, and the mechanical interaction of the clad and base materials under load. This work focuses on the final issue: the mechanical interaction of the base and clad under creep-fatigue conditions. Depending on the relative mechanical properties of the two materials the clad may substantially influence the long-term cyclic response of the structural system or its effect might be negligible. To quantify the effect of different clad material properties we develop an efficient method for simulating pressurized cladded components in the limiting case where the section of interest is far from structural discontinuities. Using this method we evaluate the mechanics of the clad/base system and identify different regimes of mechanical response. The focus is on situations relevant to high temperature nuclear components: thermal-cyclic Bree-type problems and similar axisymmetric structures. The insights gained from these structural studies will form the basis for developing design rules for high-temperature, nuclear, cladded components.

Transient Study on Sodium Heat Pipe in Passive Heat Removal System of Molten Salt Reactor

2013 ◽  
Author(s):  
Chenglong Wang ◽  
Suizheng Qiu ◽  
Wenxi Tian ◽  
Yingwei Wu ◽  
Guanghui Su
Keyword(s):  
High Temperature ◽  
Molten Salt ◽  
Heat Pipe ◽  
Heat Removal ◽  
Heat Pipes ◽  
Molten Salt Reactor ◽  
Sodium Heat Pipe ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

High temperature heat pipes are effective devices for heat transfer, which are characterized by remarkable advantages in conductivity, isothermality and passivity. It is of significance to apply heat pipes on new concept passive residual heat removal system (PRHRS) of molten salt reactor (MSR). In this paper, the transient performance of high temperature sodium heat pipe is simulated with numerical method in the case of MSR accident. The model of the heat pipe is composed of three conjugate heat transfers, i.e. the vapor space, wick structure and wall. Based on finite element method, the governing equations and boundary conditions are solved by using FORTRAN code to acquire the profiles of the temperature, velocity and pressure for the heat pipe transient operation. The results indicated that high temperature sodium heat pipe had a good operating characteristic and removed the residual heat of fuel salt rapidly under the accident of MSR.

scholarly journals Design and Test for a High-Temperature Molten Salt Pump

2014 ◽  
Author(s):  
Zhong Li ◽  
Yuan Fu ◽  
Jianyu Zhang ◽  
Liancheng Lin ◽  
Jianping Huang ◽  
...  
Keyword(s):  
Temperature Field ◽  
Thermal Stress ◽  
High Temperature ◽  
Molten Salt ◽  
Stress And Strain ◽  
Molten Salt Reactor ◽  
Test Loop ◽  
Drive Motor ◽  
Sufficient Strength ◽  
Thermal Stress And Strain

A high-temperature molten salt pump, described as mechanical, free-surface, centrifugal, vertical-shaft, sump type, working at 500°C [932°F] to 600°C [1112°F], has been developed for the Thorium-Based Molten Salt Reactor (TMSR). Flow passage components of the pump are made of Hastelloy C-276 to ensure sufficient strength and corrosion resistance at high temperature. Also, a heat shield plug with air-cooled channels was designed to separate the drive motor, seal elements, and bearings from intense radioactivity and to keep the temperature of the flange seal below 150°C [302°F] and the temperature of the bearing below 80°C [176°F]. A dry gas seal was used so that there is zero leakage. Furthermore, some analysis of hydraulics characteristics, temperature field, thermal stress, and strain was performed to research the pump’s performance, and then the temperature field and the hydraulics were measured to validate the analysis results. The results show that the hydraulics, thermal stress, and strain meet the design value very well. The pump has been successfully operated on a LiF-NaF-KF test loop for over 250 hr. at temperatures of 500°C [932°F] to 600°C [1112°F], speeds of 1050 to 1450rpm, and flows of 15 m3/h [66 gpm] to 25 m3/h [110 gpm]. Paper published with permission.

Signatures of plutonium diversion in Molten Salt Reactor dynamics

2021 ◽  
Vol 160 ◽  
pp. 108370
Author(s):  
Alexander M. Wheeler ◽  
Ondřej Chvála ◽  
Steven Skutnik
Keyword(s):  
Molten Salt ◽  
Molten Salt Reactor ◽  
Reactor Dynamics

Analyses of production capacity of 89Sr and 90Sr in the 2 MW molten salt reactor

2021 ◽  
Vol 173 ◽  
pp. 109714
Author(s):  
Chen Wu ◽  
Chenggang Yu ◽  
Ao Zhang ◽  
Chunyan Zou ◽  
Yuwen Ma ◽  
...  
Keyword(s):  
Molten Salt ◽  
Production Capacity ◽  
Molten Salt Reactor

A new method for monitoring the redox potential of fuel salt based on the deposition of 95Nb on Hastelloy C276

2021 ◽  
Vol 109 (5) ◽  
pp. 357-365
Author(s):  
Zhiqiang Cheng ◽  
Zhongqi Zhao ◽  
Junxia Geng ◽  
Xiaohe Wang ◽  
Jifeng Hu ◽  
...  
Keyword(s):  
Redox Potential ◽  
Molten Salt ◽  
Specific Activity ◽  
Chemical Reduction ◽  
Quantitative Approach ◽  
Experimental Results ◽  
New Method ◽  
Molten Salt Reactor ◽  
Fuel Salt ◽  
Well Correlation

Abstract To develop the application of 95Nb as an indicator of redox potential for fuel salt in molten salt reactor (MSR), the specific activity of 95Nb in FLiBe salt and its deposition of 95Nb on Hastelloy C276 have been studied. Experimental results indicated that the amount of 95Nb deposited on Hastelloy C276 resulted from its chemical reduction exhibited a positive correlation with the decrease of 95Nb activity in FLiBe salt and the relative deposition coefficient of 95Nb to 103Ru appeared a well correlation with 95Nb activity in FLiBe salt. Both correlations implied that the measurement of 95Nb activity deposited on Hastelloy C276 specimen might provide a quantitative approach for monitoring the redox potential of fuel salt in MSR.

Absorption and Stripping of CO2 with a Molten Salt Slurry in a Bubble Column at High Temperature

2006 ◽  
Vol 29 (9) ◽  
pp. 1118-1121 ◽  
Author(s):  
K. Terasaka ◽  
Y. Suyama ◽  
K. Nakagawa ◽  
M. Kato ◽  
K. Essaki
Keyword(s):  
High Temperature ◽  
Molten Salt ◽  
Bubble Column
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