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Modeling The Molten Salt Reactor Experiment With The Neams System Analysis Module
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Book Synopsis Modeling the Molten Salt Reactor Experiment with the NEAMS System Analysis Module by : Adrian Leandro
Download or read book Modeling the Molten Salt Reactor Experiment with the NEAMS System Analysis Module written by Adrian Leandro and published by . This book was released on 2018 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: System analysis codes have a long history of providing best-estimate and conservative safety analysis for both light water and advanced reactor technologies. As interest continues to expand with advanced reactor concepts, system analysis codes will need revisions to accommodate the behavior of these technologies. The codes will also need to be updated to the latest numerical techniques to shorten execution time and increase the accuracy of results. One such tool that already encompasses these techniques is the System Analysis Module (SAM). An advanced reactor concept with recent interest is the Molten Salt Reactor (MSR). This concept is built upon the Molten Salt Reactor Experiment (MSRE), which provided early data and experience. Therefore, the objective of this work is to use legacy MSRE data as a basis of comparison with SAM results.Two MSRE models are developed to evaluate SAM. One model is the SAM MSRE water mockup where experimental data was collected for pressure drop measurements. The other model is the complete MSRE primary loop. The MSRE system model incorporates fluoride salt fuel/coolant with heat transfer in both the core and heat exchanger. Estimates for the core coolant temperature profiles allow this reactor to be evaluated. The primary loop model is also altered for various additional studies, such as simulating varying coolant properties and a loss of flow (LOF) response.The SAM model results for the pressure drop of the water mockup model are within 6% with measurements, which provides confidence that the models geometry is physically accurate over a range of flow rates. Coolant temperatures are also accurate for the primary loop model matching the expected axial change in temperature. Alternative coolant properties from the literature with different actinide content yield similar trends in core temperature profiles. A thermal hydraulic demonstration of a LOF transient shows the importance of coupling SAM thermal hydraulic analysis to neutronics. This coupling is essential for simulating MSR transients with system analysis codes.
Book Synopsis Multi-physics Approach to the Modelling and Analysis of Molten Salt Reactors by : Lelio Luzzi
Download or read book Multi-physics Approach to the Modelling and Analysis of Molten Salt Reactors written by Lelio Luzzi and published by Nova Novinka. This book was released on 2012 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Multi-Physics Modelling (MPM) is an innovative simulation technique that looks very promising for the employment in the field of nuclear engineering as an integrative analysis support in the design development of current and innovative nuclear reactors. This book presents a Multi-Physics Modelling (MPM) approach to the analysis of nuclear reactor core behaviour, developed to study the coupling between neutronics and thermo-hydrodynamics. Reference is made to the Molten Salt Reactor, one of the innovative nuclear systems under development in the framework of the Generation IV International Forum, but the same methodology can be applied to other reactor systems.
Book Synopsis Study of the Dynamic Behavior of Molten-Salt Reactors by : Vikram Singh (Researcher in nuclear engineering)
Download or read book Study of the Dynamic Behavior of Molten-Salt Reactors written by Vikram Singh (Researcher in nuclear engineering) and published by . This book was released on 2019 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Molten-Salt Reactors (MSR) are a Gen-IV reactor concept being investigated by companies and institutions alike. These reactors are considerably different from the current fleet of Light-Water Reactors and outside the experience base of most Nuclear Engineers. The fluid nature of the fuel leads to delayed temperature and reactivity feedback effects unique to each reactor design that need to be characterized to determine operability and safety limits. Moreover, the design space under consideration encompasses various fuel-cycles, neutron spectra, and materials. This requires a modeling methodology that can be applied to the breadth of designs under development and is the subject of ongoing research at the University of Tennessee. This thesis presents a dynamic modeling approach that was validated against experimental data from the Molten-Salt Reactor Experiment. The developed lumped-parameter models are nonlinear and represent time rate of change in mass and energy in all parts of the reactor. Reactivity feedbacks arising from changes in temperature and neutron poison concentrations are taken into account. These models can be used to study both the time and frequency response to perturbations caused during normal operating conditions and during anomalies resulting from failure of certain components. The thesis incorporates material published in a series of journal articles and conference proceedings. The validated modeling approach is detailed, and all equations and parameters of interest are listed. Three reactor systems are modeled, namely the Molten-Salt Reactor Experiment, two-fluid Molten-Salt Breeder Reactor, and a plant-level model based on the Molten-Salt Demonstration Reactor. Application of the models to studying operational anomalies, dynamic effects of xenon and samarium neutron poisons, parametric sensitivity analysis, and load-following are also presented. From the investigated perturbations for the presented designs, it is found that these systems are stable and self-regulating. Modeling results suggest that well-designed MSRs with adequate negative feedback exhibit excellent load-following characteristics that can be leveraged to engineer control systems offering a great deal of autonomy.
Book Synopsis Global Progress on Molten Salt Reactors by : Thomas James Dolan
Download or read book Global Progress on Molten Salt Reactors written by Thomas James Dolan and published by Elsevier. This book was released on 2024-02-05 with total page 294 pages. Available in PDF, EPUB and Kindle. Book excerpt: Global Progress on Molten Salt Reactors: A Companion to Dolan’s Molten Salt Reactors and Thorium Energy, Second Edition presents global perspectives on the latest research and technological advances. Each case study utilizes a comprehensive template that guides the reader through country specific research. Useful data which can be applied to work and research is included, along with a list of references for further research. Researchers, professional engineers and policymakers will gain a broad picture of worldwide MSR activity and a deep understanding of how theory and practical guidance is applied in a variety of settings, including budgets, approaches and constraints. Provides a collection of case studies from 23 countries, presenting their latest research and activities on Molten Salt Reactors Based on chapter 26 of the first edition of Dolan’s Molten Salt Reactors and Thorium Energy, this companion title presents expanded and more complete coverage of global activities and research Includes advanced technologies, reactor designs and safety and management strategies
Book Synopsis Liquid-fueled Molten Salt Reactor Modeling and Uncertainty Analysis for Safeguards Purposes by : Andre Vidal Soares
Download or read book Liquid-fueled Molten Salt Reactor Modeling and Uncertainty Analysis for Safeguards Purposes written by Andre Vidal Soares and published by . This book was released on 2022 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: With the recent interest in advanced nuclear reactors, the need for developing nuclear material accounting strategies arise. Especially in liquid-fueled molten salt reactors, which preclude the ability to count fixed amount of material in a discrete way, as opposed to the traditional counting method widely used in the current nuclear fleet. Usually, these reactor concepts involve online fuel processing where fuel and its products flow within many streams along the plant. In computational modeling, this feature requires high fidelity depletion schemes, including the addition of feed and removal capabilities that can simulate their regular operation. Estimating isotopic inventory under regular and diversion scenarios would provide an insight on which reactor parameters could be tracked to timely detect diversion of special nuclear material. To achieve this, a depletion model was developed for the Molten Salt Demonstration Reactor (with minor adaptations) in Serpent 2 and SCALE. Feed and removal capabilities were implemented in the Serpent latest release and is under testing in SCALE 6.3 beta versions. Plutonium diversion scenarios are modeled and their impact on regular operation of the reactor is analyzed. The SCALE module Sampler is used to estimate nuclear data uncertainties propagated along the depletion interval. Several isotopes presented changes in their concentrations given a 10SQ plutonium diversion protracted scenario. Some examples are fission products such as 89Sr (1.06% change and 0.58% uncertainty), 91Y (1.92% change and 0.43% uncertainty), 113Cd (-5.00% change and 3.31% uncertainty), 151Eu (-3.84% change and 2.70% uncertainty) and also actinides like 241Am (-6.88% change and 2.23% uncertainty), 242mAm (-6.22% change and 4.88% uncertainty) and 242Cm (-4.50% change and 3.84% uncertainty). Preliminary sensitivity analyses were performed using TSUNAMI and Sampler. Results revealed that 238U(n,[gamma]) plays an important role in contributing to the uncertainty in parameters (e.g., k-inf) and nuclide concentrations (e.g., 239Pu and 241Pu). Future work includes the full analyses of scenarios - including abrupt ones, which are already modeled, and a comprehensive sensitivity study on nuclide concentrations - including fission products and higher actinides. Moreover, methods to improve nuclear covariance data - guided by the sensitivity study - will also be pursued using Bayesian methods and machine learning techniques.
Book Synopsis Molten-Salt Reactor Program Semiannual Progress Report for Period Ending ... by : Oak Ridge National Laboratory
Download or read book Molten-Salt Reactor Program Semiannual Progress Report for Period Ending ... written by Oak Ridge National Laboratory and published by . This book was released on 1965-02 with total page 198 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Predicted and Observed Nuclear Characteristics of the Molten Salt Reactor Experiment by :
Download or read book Predicted and Observed Nuclear Characteristics of the Molten Salt Reactor Experiment written by and published by . This book was released on 1965 with total page 6 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Complete Sensitivity/Uncertainty Analysis of LR-0 Reactor Experiments with MSRE FLiBe Salt and Perform Comparison with Molten Salt Cooled and Molten Salt Fueled Reactor Models by :
Download or read book Complete Sensitivity/Uncertainty Analysis of LR-0 Reactor Experiments with MSRE FLiBe Salt and Perform Comparison with Molten Salt Cooled and Molten Salt Fueled Reactor Models written by and published by . This book was released on 2016 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: In September 2016, reactor physics measurements were conducted at Research Centre Rez (RC Rez) using the FLiBe (2 7LiF + BeF2) salt from the Molten Salt Reactor Experiment (MSRE) in the LR-0 low power nuclear reactor. These experiments were intended to inform on neutron spectral effects and nuclear data uncertainties for advanced reactor systems using FLiBe salt in a thermal neutron energy spectrum. Oak Ridge National Laboratory (ORNL), in collaboration with RC Rez, performed sensitivity/uncertainty (S/U) analyses of these experiments as part of the ongoing collaboration between the United States and the Czech Republic on civilian nuclear energy research and development. The objectives of these analyses were (1) to identify potential sources of bias in fluoride salt-cooled and salt-fueled reactor simulations resulting from cross section uncertainties, and (2) to produce the sensitivity of neutron multiplication to cross section data on an energy-dependent basis for specific nuclides. This report provides a final report on the S/U analyses of critical experiments at the LR-0 Reactor relevant to fluoride salt-cooled high temperature reactor (FHR) and liquid-fueled molten salt reactor (MSR) concepts. In the future, these S/U analyses could be used to inform the design of additional FLiBe-based experiments using the salt from MSRE.
Book Synopsis Evaluation of the U.S. Department of Energy's Alternatives for the Removal and Disposition of Molten Salt Reactor Experiment Fluoride Salts by : National Research Council
Download or read book Evaluation of the U.S. Department of Energy's Alternatives for the Removal and Disposition of Molten Salt Reactor Experiment Fluoride Salts written by National Research Council and published by National Academies Press. This book was released on 1997-02-26 with total page 147 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book discusses the technical alternatives for cleanup of radioactive fluoride salts that were the fuel for the Molten Salt Reactor Experiment, a novel nuclear reactor design that was tested in the 1960s at the Oak Ridge National Laboratory in Tennessee. These fluoride salts pose an unusual cleanup challenge. The book discusses alternatives for processing and removing the salts based on present knowledge of fluoride salt chemistry and nuclear reactions of the radioactive constituents.
Book Synopsis Multiphysics simulations of Molten Salt Reactors using the Moltres code by : Mateusz Pater
Download or read book Multiphysics simulations of Molten Salt Reactors using the Moltres code written by Mateusz Pater and published by . This book was released on 2019 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The aim of this paper was to model and simulate Molten Salt Reactor (MSR) specific phenomena, to analyzethem on an example of two different MSR designs, and to assess the accuracy of different codes.Although inherent safety features and interesting nuclear properties of MSRs present a number of poten-tial benefits for the field of nuclear energy production, there is an evident lack of experimental data, provenprototypes, and materials being able to withstand extreme conditions. In order to pave the way for MSRs aconsiderable amount of modeling and engineering work must be done. There are only few numerical tools whichare capable of simulating the complex behavior of such reactors properly. One of these codes, Moltres, is anapplication of MOOSE, a C++ based multiphysics simulation environment, and was utilized extensively in thisproject along with a Monte Carlo code called Serpent.The Serpent code was used to generate group constants for the multigroup diffusion equation solver em-bedded in Moltres, which is coupled with delayed neutron precursor (DNP) and thermal hydraulics equations.Simplified models of the Oak Ridge Nuclear Laboratory's Molten Salt Reactor Experiment (MSRE) and ofSeaborg Technologies' Compact Molten Salt Reactor (CMSR) were created in the Serpent and in Gmsh soft-ware which was used to generate a mesh file for Moltres. Moltres simulations took advantage of a symmetryin the two dimensional geometrical models and included only the nuclear reactor core and the effect of heatremoval in the primary heat exchangers. Phenomena such as DNP transport with the moving fuel and crosssection change with the temperature were duly accounted for.Results for the MSRE case were compared to the original design calculations and a good qualitative anddecent quantitative agreement was found. Some propositions to be included in Seaborg Technologies' reactordesign were produced. Two transients, Unprotected Loss Of Flow and Unprotected Loss Of Heat Sink, werelooked into. The Moltres code proved to be a valuable tool to simulate MSRs. However, many uncertaintiesin the input data and numerous model simplifications caused the results to be only preliminary and requiringmore refinemen.
Book Synopsis Operation of the Molten Salt Reactor Experiment by :
Download or read book Operation of the Molten Salt Reactor Experiment written by and published by . This book was released on 1965 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Thermal Stress Considerations in the Molten Salt Reactor Experiment by :
Download or read book Thermal Stress Considerations in the Molten Salt Reactor Experiment written by and published by . This book was released on 1962 with total page 7 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis A Descriptive Model of the Molten Salt Reactor Experiment After Shutdown by :
Download or read book A Descriptive Model of the Molten Salt Reactor Experiment After Shutdown written by and published by . This book was released on 1996 with total page 66 pages. Available in PDF, EPUB and Kindle. Book excerpt: During FY 1995 considerable progress was made toward gaining a better understanding of the chemistry and transport processes that continue to govern the behavior of the Molten Salt Reactor Experiment (MSRE). As measurements in the MSRE proceed, laboratory studies continue, and better analyses are available, our understanding of the state of the MSRE and the best path toward remediation improves. Because of the immediate concern about the deposit in the auxiliary charcoal bed (ACB), laboratory studies in the past year focused on carbon-fluorine chemistry. Secondary efforts were directed toward investigation of gas generation from MSRE salts by both radiolytic and nonradiolytic pathways. In addition to the laboratory studies, field measurements at the MSRE provided the basis for estimating the inventory of uranium and fluorine in the ACB. Analysis of both temperature and radiation measurements provided independent and consistent estimates of about 2.6 kg of uranium deposited in the top of the ACB. Further analysis efforts included a refinement in the estimates of the fuel- salt source term, the deposited decay energy, and the projected rate of radiolytic gas generation. This report also provides the background material necessary to explain new developments and to review areas of particular interest. The detailed history of the MSRE is extensively documented and is cited where appropriate. This work is also intended to update and complement the more recent MSRE assessment reports.
Book Synopsis Computational Modeling of Flow in a 10MWe Natural Convection Molten Salt Reactor by : G. M. Strombach
Download or read book Computational Modeling of Flow in a 10MWe Natural Convection Molten Salt Reactor written by G. M. Strombach and published by . This book was released on 2020 with total page 356 pages. Available in PDF, EPUB and Kindle. Book excerpt: This research investigates the use of computational fluid dynamics (CFD) to simulate flow in a practical power system that includes a natural-convection molten salt reactor (MSR). Included herein are five sets of simulations, which start simply and build in complexity.Unique aspects of this research:0́ØEach simulation explores realistic design aspects of practical MSRs; i.e., those used for electric power generation, etc.0́ØEach simulation uses internal heat generation (instead of surface/external heat flux) to reflect energy released in the reactor vessel.0́ØAn actual fuel salt was used for three of the five simulation sets. It is based on a mixture of lithium & beryllium fluoride salt, known as FLiBe.0́ØSimulations that use FLiBe as the working fluid include a newly developed relation - variable energy source/power density - for energy released in the reactor vessel. This unique approach is based on operational data from actual MSRs. It reflects changes in reactivity (and thus power density) as a function of salt temperature and thus captures the negative temperature coefficient effect.First is a series of 16 cases, using simple cylinders for the reactor and heat exchanger, with water as the working fluid. These determine the size, shape & elevation difference between the reactor vessel and heat exchanger. To achieve natural convection flow within a specified temperature range, the minimum relative elevation difference between the reactor and heat exchanger is 12 feet. CFD results in the range of interest match analytic values within 4.4%.Next is a series of 10 cases, using baffled cylinders for the reactor and heat exchanger, with FLiBe salt as the working fluid. These determine the elevation difference between the reactor vessel & heat exchanger. To achieve natural convection flow within a specified temperature range, the minimum relative elevation difference between the reactor and heat exchanger is also 12 feet. CFD results in the range of interest match analytic values within 0.55%.The third set is a benchmarking template for a test rig built at the University of Idaho campus in Idaho Falls. At the point of incipient natural convection flow, the temperature difference from the simulation is within 2.45% of the value predicted by analytic means.Next is simulation of a realistic MSR system. It includes a reactor vessel with complex internal structure, to model an array of graphite moderator bars. This confirms that a relative difference in elevation of 12 feet meets the design criteria for the specified temperature range.Finally, a simulation of a different realistic MSR system which uses an external reflector rather than internal moderator bars. The original design has a difference in elevation of 4 feet. Simulations show that this does not meet the design criteria of achieving the recommended temperature range.These results suggest that it is possible to simulate a realistic natural convection molten salt reactor. Using the techniques herein, one can obtain valuable engineering information to assist in the design of practical power systems.
Book Synopsis Status of Molten Salt Reactor Technology by : IAEA
Download or read book Status of Molten Salt Reactor Technology written by IAEA and published by International Atomic Energy Agency. This book was released on 2023-11-27 with total page 319 pages. Available in PDF, EPUB and Kindle. Book excerpt: Written to assist individuals in academia and industry and in relevant regulatory and policy roles, this publication provides a summary of the current knowledge on the status of research, technological developments, reactor designs and experiments in the area of advanced reactors that are fueled or cooled by a molten salt. Identification of challenges and areas where research and development are still required in preparation for commercial deployment gives context to current and planned work. The aim of this publication is to share information on programs and projects on molten salt reactors in Member States which will shape future collaborative efforts.
Book Synopsis Simulation of Irradiation of a Molten Salt Loop at the MIT Reactor by : Loukas Carayannopoulos
Download or read book Simulation of Irradiation of a Molten Salt Loop at the MIT Reactor written by Loukas Carayannopoulos and published by . This book was released on 2023 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Over the past decade or so, molten salt reactors (MSR) have gained a lot of interest within the nuclear energy community, with two of the ten reactor designs supported by the Department of Energy's (DOE) Advanced Reactor Development Program being MSRs. Commercializing MSR technology requires new experimental facilities to improve understanding of molten salt behavior in reactor-like environments. The Nuclear Energy University Program approved a project to design and build a molten salt test bed that will be irradiated by the MIT Reactor (MITR), which will provide testing capabilities that have not existed since the shutdown of the Molten Salt Reactor Experiment (MSRE) in 1969. The main experimental goals of the project are (1) to build a molten salt loop that operates between 550° C and 700° C and is irradiated by neutrons from the MITR to duplicate conditions in a molten salt reactor, (2) to produce data regarding the transport, diffusion, and dissolution of tritium and radionuclides in molten salts, and (3) to provide a facility for testing chemistry control, salt cleanup, tritium control, and instrumentation. To safely design this facility, an understanding of the radioactivity generated in the loop is needed. The purpose of this work is to model the irradiation of the salt loop, using MCNP and Serpent, to determine the necessary amount of radiation shielding and the activation of different salts proposed for use in MSRs. The salts considered are FLiBe, LiF-BeF[subscript 2]-ZrF[subscript 4]-UF[subscript 4] used in the MSRE, LiF-BeF[subscript 2]-UF[subscript 4] suggested as a fuel salt by Terrestrial Energy and Flibe Energy, LiF-BeF[subscript 2]-ThF[subscript 4] suggested as a blanket salt by Flibe Energy, and NaCl-UCl[subscript 3] suggested as a fuel salt by TerraPower. FLiBe will generate 1.413 ± 0.024 mCi/hr of tritium, with all other fluoride salts generating similar quantities, and a total of 1413 ± 24 Ci over a 1000-hour period -- the maximum continuous operation time proposed for the facility. The maximum radioactivity produced in 1000 hours of operation is 546.9 Ci in the chloride salt. The quantities of tritium and other radioactive products formed in each of the salts make this facility an important tool for the development of MSR technology.
Book Synopsis Thermal Analysis to Support Decommissioning of the Molten Salt Reactor Experiment by : C. D. Sulfredge
Download or read book Thermal Analysis to Support Decommissioning of the Molten Salt Reactor Experiment written by C. D. Sulfredge and published by . This book was released on 1996 with total page 65 pages. Available in PDF, EPUB and Kindle. Book excerpt:
