Modelling Frozen Salt Films in a Molten Salt Fast Reactor

2018 ◽  
Author(s):  
Gregory M. Cartland-Glover ◽  
Stefano Rolfo ◽  
Alex Skillen ◽  
David R. Emerson ◽  
Charles Moulinec ◽  
...  
Keyword(s):  
Heat Exchanger ◽  
Molten Salt ◽  
Fast Reactor ◽  
Energy Production ◽  
Nuclear Energy ◽  
Numerical Models ◽  
Reactor Core ◽  
Separated Flow ◽  
Flow And Heat Transfer ◽  
Innovative Solutions

Molten salt reactors are a very promising option for the development of highly innovative solutions for the nuclear energy production of the future. The techniques used to model thermal hydraulics of a molten salt fast reactor when frozen salt wall technology is applied to the core vessel wall are presented here for 2D numerical models of a hyperboloid reactor core region with a heat exchanger was applied in Code_Saturne. A 3D simulation of the fluid flow and heat transfer with 16 recirculation loops containing the heat exchangers is also presented. It was found that there is strong cooling in separated flow regions in the external heat exchanger, which freezes where the porous model is applied.

scholarly journals Investigation of thermodynamic factors influencing Thorium reactor efficiencies

2015 ◽  
Vol 2 ◽  
pp. 14-31
Author(s):  
Jarrod Glass ◽  
Anthony Burgess ◽  
Takuya Okugawa
Keyword(s):  
Molten Salt ◽  
Atmospheric Pressure ◽  
Energy Production ◽  
Nuclear Energy ◽  
Nuclear Reactors ◽  
Reactor Core ◽  
Thermodynamic Efficiency ◽  
Power Flux ◽  
Factors Influencing ◽  
Water Reactors

In this meta-study, the major forms of thorium based nuclear reactors were compared using thermodynamic parameters to find which reactor type holds the highest thermodynamic efficiency and hence, determine which reactor would be most beneficial to research further and implement for energy production. Our study found that molten salt reactors had the best thermodynamic efficiency and also runs at one atmospheric pressure, making it safer than conventional water reactors. The findings in this study show molten salt reactors would be the most efficient reactor to replace standard water reactors, which dominate the market in use of nuclear energy production. This study found a strong link between the thermal efficiency of the plant and the pressure and temperature at which it runs. Reactor core volumes also appeared to have a small effect on the efficiencies. Power flux density was calculated for each style of reactor and compared to other parameters but no distinct relationship was found between them. 

scholarly journals Heat exchanger design studies for molten salt fast reactor

2019 ◽  
Vol 5 ◽  
pp. 12
Author(s):  
Uğur Köse ◽  
Ufuk Koç ◽  
Latife Berrin Erbay ◽  
Erdem Öğüt ◽  
Hüseyin Ayhan
Keyword(s):  
Heat Exchanger ◽  
Molten Salt ◽  
Fast Reactor ◽  
Heat Exchangers ◽  
Temperature Drop ◽  
Freezing Temperature ◽  
Fuel Temperature ◽  
Design Studies ◽  
The Core ◽  
Heat Exchanger Design

In this study, conceptual design for primary heat exchanger of the Molten Salt Fast Reactor is made. The design was carried out to remove the produced heat from the reactor developed under the SAMOFAR project. Nominal power of the reactor is 3 GWth and it has 16 heat exchangers. There are several requirements related to the heat exchanger. To sustain the steady-state conditions, heat exchangers have to transfer the heat produced in the core and it has to maintain the temperature drop as much as the temperature rise in the core due to the fission. It should do it as fast as possible. It must also ensure that the fuel temperature does not reach the freezing temperature to avoid solidification. In doing so, the fuel volume in the heat exchanger must not exceed the specified limit. Design studies were carried out taking into account all requirements and final geometric configurations were determined. Plate type heat exchanger was adopted in this study. 3D CFD analyses were performed to investigate the thermal-hydraulic behavior of the system. Analyses were made by ANSYS-Fluent commercial code. Results are in a good agreement with limitations and requirements specified for the reactor designed under the SAMOFAR project.

scholarly journals Study of Helium Cooled Fast Reactor Core Design Fuelled by Thorium Carbide-Uranium Carbide with Modified Candle Axial Direction Scheme

2021 ◽  
Vol 2072 (1) ◽  
pp. 012002
Author(s):  
Z Su’ud ◽  
N R Galih ◽  
M Ariani
Keyword(s):  
Fast Reactor ◽  
Nuclear Power ◽  
Nuclear Energy ◽  
Reactor Core ◽  
Axial Direction ◽  
Natural Uranium ◽  
Design Calculation ◽  
Uranium Carbide ◽  
Human Need ◽  
Core Height

Abstract Human need of energy will increase time to time. Therefore, a safe, renewable, and efficient source of energy, which is Nuclear Energy, is needed. Nuclear Power Plant (NPP) is the most compatible solution to provide electricity to human race in the future. The problem that came within NPP is the danger of proliferation issues. The method that has been developed to overcome this problem is CANDLE [5] and has been modified by Prof. Zaki Su’ud (Modified CANDLE scheme). This research use Axial Modified CANDLE Scheme to Helium-Cooled Fast Reactor with Natural Uranium Carbide-Thorium Carbide as fuel and applied to various size of core as optimization. Neutronic aspect such as, burn up level, multiplication factor, and conversion ratio are utilized in this paper in order to analyse the behaviour of the reactor. Other than that, percentage of Uranium has been varied to reduce power peaking. The neutronic calculation has been done using SRAC and core design calculation by FI-ITB-CH1. This research concludes that power peaking reduction is able to achieve by combining Uranium Carbide and Thorium Carbide to the fuel. The optimum reactor design reached at 360 cm of core radius and 303 cm of core height.

scholarly journals An Eulerian Single-Phase Transport Model for Solid Fission Products in the Molten Salt Fast Reactor: Development of an Analytical Solution for Verification Purposes

2021 ◽  
Vol 9 ◽  
Author(s):  
Andrea Di Ronco ◽  
Stefano Lorenzi ◽  
Francesca Giacobbo ◽  
Antonio Cammi
Keyword(s):  
Boundary Conditions ◽  
Molten Salt ◽  
Fast Reactor ◽  
Liquid Fuel ◽  
Mixed Type ◽  
Single Phase ◽  
Transport Model ◽  
Reactor Core ◽  
Fission Products ◽  
Phase Transport

Nuclear reactor modeling has been shifting, over the last decades, towards full-core multiphysics analysis due to the ever-increasing safety requirements and complexity of the designs of innovative systems. This is particularly true for liquid-fuel reactor concepts such as the Molten Salt Fast Reactor (MSFR), given their strong intrinsic coupling between thermal-hydraulics, neutronics and fuel chemistry. In the MSFR, fission products (FPs) are originated within the liquid fuel and are carried by the fuel flow all over the reactor core and through pumping and heat exchange systems. Some of FP species, in the form of solid precipitates, can represent a major design and safety challenge, e.g., due to deposition on solid boundaries, and their distribution in the core is relevant to the design and safety analysis of the reactor. In this regard it is essential, both for the design and the safety assessment of the reactor, the capability to model the transport of solid FPs and their deposition to the boundary (e.g., wall or heat exchanger structures). To this aim, in this study, models of transport of solid FPs in the MSFR are developed and verified. An Eulerian single-phase transport model is developed and integrated in a consolidated multiphysics model of the MSFR based on the open-source CFD library OpenFOAM. In particular, general mixed-type deposition boundary conditions are considered, to possibly describe different kinds of particle-wall interaction mechanisms. For verification purposes, analytical solutions for simple case studies are derived ad hoc based on the extension of the classic Graetz problem to linear decay, distributed source terms and mixed-type boundary conditions. The results show excellent agreement between the two models, and highlight the effects of decay and deposition phenomena of various intensity. The resulting approach constitutes a computationally efficient tool to extend the capabilities of CFD-based multiphysics MSFR calculations towards the simulation of solid fission products transport.

Dynamic mode decomposition for the stability analysis of the Molten Salt Fast Reactor core

2020 ◽  
Vol 362 ◽  
pp. 110529 ◽  
Author(s):  
Andrea Di Ronco ◽  
Carolina Introini ◽  
Eric Cervi ◽  
Stefano Lorenzi ◽  
Yeong Shin Jeong ◽  
...  
Keyword(s):  
Stability Analysis ◽  
Molten Salt ◽  
Fast Reactor ◽  
Reactor Core ◽  
Dynamic Mode Decomposition ◽  
Dynamic Mode ◽  
Mode Decomposition ◽  
The Stability

Dynamic Simulation Research on Primary Coolant System of Sodium Cooled Fast Reactor

2012 ◽  
Author(s):  
Yang Yu ◽  
Yun Guo
Keyword(s):  
Fast Reactor ◽  
Reactor Core ◽  
Safety Analysis ◽  
Operating Conditions ◽  
Cold Pool ◽  
Primary Coolant ◽  
Simulation Research ◽  
Flow And Heat Transfer ◽  
Comparison Of The Results ◽  
Pool Type

The Chinese Experimental Fast Reactor (CEFR) is a 65MWt/20MWe sodium cooled fast reactor. It is a pool-type reactor where the reactor and other internals such as pumps and intermediate heat exchangers (IHX) are immersed in a sodium pool. In this paper a one-dimensional dynamic code was developed to model the primary sodium circuit which included the reactor core, IHX, pumps, hot and cold pool etc. Moreover, the model of the property of sodium flow and heat transfer correlations was collected and compiled. This paper also discusses the mathematical models of various components of the primary sodium circuit, the numerical techniques to solve the models, the thermal-hydraulic studies of some design basis events such as the loss of primary pump or secondary pump accident etc, the comparison of the results of the code with that of the safety analysis report. Studies were conducted simulating both full and low power operating conditions. The dynamic code has been validated, and the results show that it has a benign response to some typical accidents. Finally, the model and code derived in this paper could be used in the safety analysis of pool-type sodium cooled fast reactor, and adopted in the development of CEFR simulation platform.

Coupled study of the Molten Salt Fast Reactor core physics and its associated reprocessing unit

2014 ◽  
Vol 64 ◽  
pp. 430-440 ◽  
Author(s):  
X. Doligez ◽  
D. Heuer ◽  
E. Merle-Lucotte ◽  
M. Allibert ◽  
V. Ghetta
Keyword(s):  
Molten Salt ◽  
Fast Reactor ◽  
Reactor Core

Feasibility of Lead Fast Reactor Heat Exchanger Tube Online Monitoring

2021 ◽  
Author(s):  
S. W. Glass ◽  
M. S. Good ◽  
E. H. Hirt
Keyword(s):  
Heat Exchanger ◽  
Molten Salt ◽  
Fast Reactor ◽  
Heat Exchangers ◽  
Management Approach ◽  
Corrosion Monitoring ◽  
Heat Exchanger Tube ◽  
Torsional Mode ◽  
Higher Temperature ◽  
Exchanger Tube

Abstract Online structural health corrosion monitoring in advanced lead fast reactor heat exchangers and molten salt reactor heat exchangers is desirable for detecting tube degradation prior to leaks that may allow mixing of heat exchanger fluids or release of radiological contamination beyond the design containment boundary. This program demonstrates feasibility for a torsional mode sensor to attach to the outside of a long (30-m) heat-exchanger tube in the stagnant flow area where the tube joins the heat-exchanger plenum and where it is possible to protect a sensor and cable from high-force flows. The sensor must be connected by a cable to a monitoring instrument near the heat exchanger. The sensor and cable management approach will be impractical to implement on existing heat exchangers; rather, sensors must be installed in conjunction with heat exchanger fabrication. Previous work has shown the ability of low-temperature lead zirconate titanate (PZT) piezoceramic sensors to detect anomalies of interest in 3-m tubes. These sensors have subsequently been extended to a 30-m tube more representative of commercial power heat exchanger designs. The program will continue to investigate higher-temperature piezoelectric ceramics and long-term performance of high-temperature adhesives and sealants for 350 C lead reactor environments and higher-temperature (700 °C) molten salt environments.

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