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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
Download 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 full books in PDF, epub, and Kindle. Read online 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 ebook anywhere anytime directly on your device. Fast Download speed and no annoying ads. We cannot guarantee that every ebooks is available!
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 Status Report on Scoping Reactor Physics and Sensitivity/Uncertainty Analysis of LR-0 Reactor Molten Salt Experiments by :
Download or read book Status Report on Scoping Reactor Physics and Sensitivity/Uncertainty Analysis of LR-0 Reactor Molten Salt Experiments written by and published by . This book was released on 2016 with total page 36 pages. Available in PDF, EPUB and Kindle. Book excerpt: Experiments are being planned at Research Centre Rež (RC Rež) to use the FLiBe (2 7LiF-BeF2) salt from the Molten Salt Reactor Experiment (MSRE) to perform reactor physics measurements in the LR-0 low power nuclear reactor. These experiments are intended to inform on neutron spectral effects and nuclear data uncertainties for advanced reactor systems utilizing FLiBe salt in a thermal neutron energy spectrum. Oak Ridge National Laboratory (ORNL) is performing sensitivity/uncertainty (S/U) analysis of these planned experiments as part of the ongoing collaboration between the United States and the Czech Republic on civilian nuclear energy research and development. The objective of these analyses is to produce the sensitivity of neutron multiplication to cross section data on an energy-dependent basis for specific nuclides. This report provides a status update 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. The S/U analyses will be used to inform design of FLiBe-based experiments using the salt from MSRE.
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 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 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 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 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 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.
Download or read book Aborigenes written by and published by . This book was released on 1988 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fluid Dynamic Studies of the Molten-Salt Reactor Experiment (MSRE) Core by :
Download or read book Fluid Dynamic Studies of the Molten-Salt Reactor Experiment (MSRE) Core written by and published by . This book was released on 1970 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fluid Fuel Reactors by : James A. Lane
Download or read book Fluid Fuel Reactors written by James A. Lane and published by . This book was released on 1958 with total page 1016 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis All that is Solid Melts Into Air by : Marshall Berman
Download or read book All that is Solid Melts Into Air written by Marshall Berman and published by Verso. This book was released on 1983 with total page 388 pages. Available in PDF, EPUB and Kindle. Book excerpt: The experience of modernization -- the dizzying social changes that swept millions of people into the capitalist world -- and modernism in art, literature and architecture are brilliantly integrated in this account.
Book Synopsis Molten Salt Reactor Experiment Facility (Building 7503) Standards by :
Download or read book Molten Salt Reactor Experiment Facility (Building 7503) Standards written by and published by . This book was released on 1996 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: This is the Phase 2 (adherence) assessment plan for the Building 7503 Molten Salt Reactor Experiment (MSRE) Facility standards/requirements identification document (S/RID). This document outlines the activities to be conducted from FY 1996 through FY 1998 to ensure that the standards and requirements identified in the MSRE S/RID are being implemented properly. This plan is required in accordance with the Department of Energy Implementation Plan for Defense Nuclear Facilities Safety Board Recommendation 90-2, November 9, 1994, Attachment 1A. This plan addresses the major aspects of the adherence assessment and will be consistent with Energy Systems procedure QA-2. 7 ''Surveillances.''
Book Synopsis Thermal Neutron Scattering by : Peter A. Egelstaff
Download or read book Thermal Neutron Scattering written by Peter A. Egelstaff and published by . This book was released on 1965 with total page 548 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Design of a Californium Source-driven Measurement System for Accountability of Material Recovered from the Molten Salt Reactor Experiment Charcoal Bed by :
Download or read book Design of a Californium Source-driven Measurement System for Accountability of Material Recovered from the Molten Salt Reactor Experiment Charcoal Bed written by and published by . This book was released on 1998 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Molten Salt Reactor Experiment Facility (MSRE) operated from 1965 to 1969. The fuel was a molten salt that flowed through the reactor core which consisted of uranium tetrafluoride with molten lithium and beryllium salt used as the coolant. In 1968 the fuel was switched from 235U to 233U. The Molten Salt Reactor Experiment was canceled in 1969 at which time approximately 4800 kg of salt was transferred to the fuel drain tanks. There was about 36.3 kg of uranium, 675 grams of plutonium and various fission products present in the fuel salt. The salt was allowed to solidify in the fuel drain tanks. The salt was heated on a yearly basis to recombine the fluorine gas with the uranium salt mixture. In March 1994, a gas sample was taken from the off gas system that indicated 233U had migrated from the fuel drain tank system to the off gas system. It was found that approximately 2.6 kg of uranium had migrated to the Auxiliary Charcoal Bed (ACB). The ACB is located in the concrete-lined charcoal bed cell which is below ground level located outside the MSRE building. Therefore, there was a concern for the potential of a nuclear criticality accident, although water would have to leak into the chamber for a criticality accident to occur. Unstable carbon/fluorine compounds were also formed when the fluorine reacted with the charcoal in the charcoal bed. The purpose of the proposed measurement system was to perform an accountability measurement to determine the fissile mass of 233U in the primary vessel. The contents of the primary containment assembly will then be transferred to three smaller containers for long term storage. Calculations were performed using MCNP-DSP to determine the configuration of the measurement system. The information obtained from the time signatures can then be compared to the measurement data to determine the amount of 233U present in the primary containment assembly.
Book Synopsis Frequency-response Testing of the Molten-salt Reactor Experiment by : Robert Cecil Steffy
Download or read book Frequency-response Testing of the Molten-salt Reactor Experiment written by Robert Cecil Steffy and published by . This book was released on 1969 with total page 117 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Volcanoes written by John P. Lockwood and published by John Wiley & Sons. This book was released on 2013-04-26 with total page 677 pages. Available in PDF, EPUB and Kindle. Book excerpt: Volcanoes are essential elements in the delicate global balance of elemental forces that govern both the dynamic evolution of the Earth and the nature of Life itself. Without volcanic activity, life as we know it would not exist on our planet. Although beautiful to behold, volcanoes are also potentially destructive, and understanding their nature is critical to prevent major loss of life in the future. Richly illustrated with over 300 original color photographs and diagrams the book is written in an informal manner, with minimum use of jargon, and relies heavily on first-person, eye-witness accounts of eruptive activity at both "red" (effusive) and "grey" (explosive) volcanoes to illustrate the full spectrum of volcanic processes and their products. Decades of teaching in university classrooms and fieldwork on active volcanoes throughout the world have provided the authors with unique experiences that they have distilled into a highly readable textbook of lasting value. Questions for Thought, Study, and Discussion, Suggestions for Further Reading, and a comprehensive list of source references make this work a major resource for further study of volcanology. Volcanoes maintains three core foci: Global perspectives explain volcanoes in terms of their tectonic positions on Earth and their roles in earth history Environmental perspectives describe the essential role of volcanism in the moderation of terrestrial climate and atmosphere Humanitarian perspectives discuss the major influences of volcanoes on human societies. This latter is especially important as resource scarcities and environmental issues loom over our world, and as increasing numbers of people are threatened by volcanic hazards Readership Volcanologists, advanced undergraduate, and graduate students in earth science and related degree courses, and volcano enthusiasts worldwide. A companion website is also available for this title at www.wiley.com/go/lockwood/volcanoes
