Experimental Modelling of a Molten Salt Reactor Concept

2013 ◽  
Author(s):  
Bogdán Yamaji ◽  
Attila Aszódi
Keyword(s):  
Molten Salt ◽  
Experimental Model ◽  
Fast Reactor ◽  
Measurement Data ◽  
Internal Heat ◽  
Working Fluid ◽  
Experimental Modelling ◽  
The Core ◽  
Single Region ◽  
Piv Measurement

Based on the MSFR (Molten Salt Fast Reactor) reactor concept proposed within the framework of the EVOL (Evaluation and Viability of Liquid Fuel Fast Reactor System, EU FP7) international research project a scaled and segmented experimental model of the MSFR and first measurement result will be presented in the paper. MSFR is a single region, homogeneous liquid fuelled fast reactor concept. The reactor uses fluoride-based molten salts as fuel and coolant, with fissile uranium and/or thorium and other heavy nuclei content with the purpose of applying the thorium cycle and the burn-up of transuranic elements. The concept has a single region cylindrical core with sixteen radial inlet and outlet nozzles located at the bottom and top of the core. The external circuit (internal heat exchanger, pump, pipes) is broken up in sixteen identical modules distributed around the core. A scaled and segmented experimental model of the MSFR concept was designed and built in order to carry out Particle Image Velocimetry (PIV) measurements. Purpose of the experimental mock-up is to provide measurement data for validation and benchmarking of CFD simulations, and also to study specific problems or phenomena related to the MSFR, such as design of inlet geometry, effects of internal structures, coolant mixing. The experimental model uses water as working fluid with 50 μm polyamide seeding particles added for PIV measurement. Geometrical scaling was applied in order to reduce size and necessary pumping power and the geometry represents a 90 degree segment of the original cylindrical geometry. It was not possible to maintain the nominal value of the Reynolds-number (∼1E+06 for the core) however a highly turbulent flow (Re>1E+05) can be reproduced in the system. Final design of the scaled and segmented plexiglas model will be presented, capabilities and limitations of the measurement assembly will be discussed together with the presentation of first measurements results.

Preliminary Thermal-Hydraulic Analyses for Designing an Experimental Model of a Molten Salt Reactor Concept

2013 ◽  
Author(s):  
Bogdán Yamaji ◽  
Attila Aszódi
Keyword(s):  
Molten Salt ◽  
Fast Reactor ◽  
Three Dimensional ◽  
Internal Heat ◽  
Molten Salt Reactor ◽  
Cfd Modelling ◽  
Scaled Model ◽  
Experimental Modelling ◽  
The Core ◽  
Single Region

Based on the MSFR (Molten Salt Fast Reactor) reactor concept presented within the framework of the EVOL (Evaluation and Viability of Liquid Fuel Fast Reactor System, EU FP7) international research project preliminary three-dimensional thermal-hydraulic analyses and the discussion of scaled experimental modelling will be presented. The MSFR concept is a single region, homogeneous liquid fuelled fast reactor. The reactor concept uses fluoride-based molten salts with fissile uranium and/or thorium and other heavy nuclei content with the purpose of applying the thorium cycle and the burn-up of transuranic elements. The concept has a single region cylindrical core with sixteen radial inlet and outlet nozzles located at the bottom and top of the core. The external circuit (internal heat exchanger, pump, pipes) is broken up into sixteen identical modules distributed around the core. Purpose of the three-dimensional computational fluid dynamics (CFD) calculations is to study the possibility of experimental investigation of the fluid flow in the core of the proposed MSFR concept using a scaled model and Particle Image Velocimetry (PIV) flow measurement technique. First the main properties of the proposed MSFR concept are introduced, and the information on other experimental thermal-hydraulic modelling of different reactors, including MSRE (Molten Salt Reactor Experiment) are summarised. With a scaled plexiglas MSFR model it would be possible to carry out flow field measurements under laboratory conditions using PIV method. Possible way of scaling are presented and a series of preliminary CFD calculations are discussed. Possibilities and limitations of such scaling and segmenting of a model and the use of water as substitute fluid for the experimental mock-up will be discussed. Objectives of such a measurement series would be validation, benchmarking of CFD calculations and codes, application of CFD modelling experience in the detailed thermal-hydraulic design of the MSFR concept, possible measurements for the study of specific problems or phenomena, for example refinement of inlet geometry, effects of internal structures, coolant mixing.

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 Neutronic benchmark of the molten salt fast reactor in the frame of the EVOL and MARS collaborative projects

2019 ◽  
Vol 5 ◽  
pp. 2 ◽  
Author(s):  
Mariya Brovchenko ◽  
Jan-Leen Kloosterman ◽  
Lelio Luzzi ◽  
Elsa Merle ◽  
Daniel Heuer ◽  
...  
Keyword(s):  
Molten Salt ◽  
Fast Reactor ◽  
Fuel Cycle ◽  
Negative Temperature ◽  
Nuclear Data ◽  
Data Set ◽  
The Core ◽  
Waste Production ◽  
Reactivity Coefficients ◽  
Core Characteristics

This paper describes the neutronic benchmarks and the results obtained by the various participants of the FP7 project EVOL and the ROSATOM project MARS. The aim of the benchmarks was two-fold: first to verify and validate each of the code packages of the project partners, adapted for liquid-fueled reactors, and second to check the dependence of the core characteristics to nuclear data set for application on a molten salt fast reactor (MSFR). The MSFR operates with the thorium fuel cycle and can be started with 233U-enriched U and/or TRU elements as initial fissile load. All three compositions were covered by the present benchmark. The calculations have confirmed that the MSFR has very favorable characteristics not present in other Gen4 fast reactors, like strong negative temperature and void reactivity coefficients, a low-fissile inventory, a reduced long-lived waste production and its burning capacities of nuclear waste produced in currently operational reactors.

Scoping Studies for a Small Modular Lead-Cooled Fast Reactor

2004 ◽  
Author(s):  
Chenggang Yu ◽  
Michael A. Smith ◽  
Earl E. Feldman ◽  
Won Sik Yang ◽  
James J. Sienicki
Keyword(s):  
Carbon Dioxide ◽  
Fast Reactor ◽  
Natural Circulation ◽  
Power Conversion ◽  
Power Converter ◽  
Working Fluid ◽  
Brayton Cycle ◽  
Primary Coolant ◽  
The Core ◽  
Scoping Studies

A scoping design study has been carried out of the feasibility of a small, 25 MWt (∼10 MWe), modular lead-cooled fast reactor coupled to an advanced power converter consisting of a gas turbine Brayton cycle that utilizes supercritical carbon dioxide as the working fluid. Major constraints of the study are an ultralong 20 year core lifetime, near zero reactivity burnup swing over the core lifetime, Pb primary coolant natural circulation heat transport, road transportability of plant modular assemblies including the reactor and guard vessels, and high Brayton cycle power conversion efficiency. It is found that the goal of a near zero reactivity burnup swing implies a low core power density that results in an unacceptably low discharge burnup.

A feasibility study of a liquid shutdown system for a single-fluid molten salt fast reactor

2021 ◽  
pp. 111053
Author(s):  
J. Fradera ◽  
P. Alberto ◽  
G. Moya ◽  
A. Bernad ◽  
A. Fernández
Keyword(s):  
Molten Salt ◽  
Feasibility Study ◽  
Fast Reactor

scholarly journals Analysis of the Molten Salt Fast Reactor using reduced-order models

2021 ◽  
Vol 140 ◽  
pp. 103909
Author(s):  
Fahad Alsayyari ◽  
Marco Tiberga ◽  
Zoltán Perkó ◽  
Jan Leen Kloosterman ◽  
Danny Lathouwers
Keyword(s):  
Molten Salt ◽  
Fast Reactor ◽  
Reduced Order Models ◽  
Reduced Order

Calculation studies of coated particles performance in sodium-cooled fast reactor

Kerntechnik ◽  
2021 ◽  
Vol 86 (1) ◽  
pp. 45-49
Author(s):  
N. V. Maslov ◽  
E. I. Grishanin ◽  
P. N. Alekseev
Keyword(s):  
Fast Reactor ◽  
Reactor Core ◽  
Heat Removal ◽  
Design Solution ◽  
Fast Neutrons ◽  
Steel Shell ◽  
Primary Circuit ◽  
Coated Particles ◽  
The Core ◽  
Fuel Assemblies

Abstract This paper presents results of calculation studies of the viability of coated particles in the conditions of the reactor core on fast neutrons with sodium cooling, justifying the development of the concept of the reactor BN with microspherical fuel. Traditional rod fuel assemblies with pellet MOX fuel in the core of a fast sodium reactor are directly replaced by fuel assemblies with micro-spherical mixed (U,Pu)C-fuel. Due to the fact that the micro-spherical (U, Pu)C fuel has a developed heat removal surface and that the design solution for the fuel assembly with coated particles is horizontal cooling of the microspherical fuel, the core has additional possibilities of increasing inherent (passive) safety and improve the competitiveness of BN type of reactors. It is obvious from obtained results that the microspherical (U, Pu)C fuel is limited with the maximal burn-up depth of ∼11% of heavy atoms in conditions of the sodium-cooled fast reactor core at the conservative approach; it gives the possibility of reaching stated thermal-hydraulic and neutron-physical characteristics. Such a tolerant fuel makes it less likely that fission products will enter the primary circuit in case of accidents with loss of coolant and the introduction of positive reactivity, since the coating of microspherical fuel withstands higher temperatures than the steel shell of traditional rod-type fuel elements.

Correcting Turbocharger Performance Measurements for Heat Transfer and Friction

2017 ◽  
Author(s):  
Mario Schinnerl ◽  
Jan Ehrhard ◽  
Mathias Bogner ◽  
Joerg Seume
Keyword(s):  
Heat Transfer ◽  
Combustion Engine ◽  
Measurement Data ◽  
Internal Heat ◽  
Friction Model ◽  
Heat Transfer Model ◽  
Transfer Model ◽  
Friction Power ◽  
Turbine Efficiency ◽  
Compressor Efficiency

The measured performance maps of turbochargers which are commonly used for the matching process with a combustion engine are influenced by heat transfer and friction phenomena. Internal heat transfer from the hot turbine side to the colder compressor side leads to an apparently lower compressor efficiency at low to mid speeds and is not comparable to the compressor efficiency measured under adiabatic conditions. The product of the isentropic turbine efficiency and the mechanical efficiency is typically applied to characterize the turbine efficiency and results from the power balance of the turbocharger. This so-called ‘thermo-mechanical’ turbine efficiency is strongly correlated with the compressor efficiency obtained from measured data. Based on a previously developed one-dimensional heat transfer model, non-dimensional analysis was carried out and a generally valid heat transfer model for the compressor side of different turbochargers was developed. From measurements and ramp-up simulations of turbocharger friction power, an analytical friction power model was developed to correct the thermo-mechanical turbine efficiency from friction impact. The developed heat transfer and friction model demonstrates the capability to properly predict the adiabatic (aerodynamic) compressor and turbine performance from measurement data obtained at a steady-flow hot gas test bench.

Sign in / Sign up

Export Citation Format

Share Document