Thermal Stress Considerations in the Molten Salt Reactor Experiment

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ISBN 13 :
Total Pages : 7 pages
Book Rating : 4.3/5 (91 download)

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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:

Thermal Analysis to Support Decommissioning of the Molten Salt Reactor Experiment

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ISBN 13 :
Total Pages : 65 pages
Book Rating : 4.:/5 (512 download)

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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:

Status of Molten Salt Reactor Technology

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Publisher : International Atomic Energy Agency
ISBN 13 : 920140722X
Total Pages : 319 pages
Book Rating : 4.2/5 (14 download)

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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.

Nuclear Science Abstracts

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ISBN 13 :
Total Pages : 1202 pages
Book Rating : 4.E/5 ( download)

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Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1970 with total page 1202 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Nuclear Science Abstracts

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ISBN 13 :
Total Pages : 1162 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Nuclear Science Abstracts by :

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1973 with total page 1162 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Operation of the Molten Salt Reactor Experiment

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ISBN 13 :
Total Pages : 13 pages
Book Rating : 4.3/5 (91 download)

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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:

Tube Plugging in the Molten-Salt Reactor Experiment Primary Heat Exchanger

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (946 download)

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Book Synopsis Tube Plugging in the Molten-Salt Reactor Experiment Primary Heat Exchanger by :

Download or read book Tube Plugging in the Molten-Salt Reactor Experiment Primary Heat Exchanger written by and published by . This book was released on 1965 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Government-wide Index to Federal Research & Development Reports

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ISBN 13 :
Total Pages : 980 pages
Book Rating : 4.E/5 ( download)

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Book Synopsis Government-wide Index to Federal Research & Development Reports by :

Download or read book Government-wide Index to Federal Research & Development Reports written by and published by . This book was released on 1966 with total page 980 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Engineering Evaluation of Proposed Alternative Salt Transfer Method for the Molten Salt Reactor Experiement for the Oak Ridge National Laboratory

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (727 download)

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Book Synopsis Engineering Evaluation of Proposed Alternative Salt Transfer Method for the Molten Salt Reactor Experiement for the Oak Ridge National Laboratory by :

Download or read book Engineering Evaluation of Proposed Alternative Salt Transfer Method for the Molten Salt Reactor Experiement for the Oak Ridge National Laboratory written by and published by . This book was released on 2009 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This evaluation was performed by Pro2Serve in accordance with the Technical Specification for an Engineering Evaluation of the Proposed Alternative Salt Transfer Method for the Molten Salt Reactor Experiment at the Oak Ridge National Laboratory (BJC 2009b). The evaluators reviewed the Engineering Evaluation Work Plan for Molten Salt Reactor Experiment Residual Salt Removal, Oak Ridge National Laboratory, Oak Ridge, Tennessee (DOE 2008). The Work Plan (DOE 2008) involves installing a salt transfer probe and new drain line into the Fuel Drain Tanks and Fuel Flush Tank and connecting them to the new salt transfer line at the drain tank cell shield. The probe is to be inserted through the tank ball valve and the molten salt to the bottom of the tank. The tank would then be pressurized through the Reactive Gas Removal System to force the salt into the salt canisters. The Evaluation Team reviewed the work plan, interviewed site personnel, reviewed numerous documents on the Molten Salt Reactor (Sects. 7 and 8), and inspected the probes planned to be used for the transfer. Based on several concerns identified during this review, the team recommends not proceeding with the salt transfer via the proposed alternate salt transfer method. The major concerns identified during this evaluation are: (1) Structural integrity of the tanks - The main concern is with the corrosion that occurred during the fluorination phase of the uranium removal process. This may also apply to the salt transfer line for the Fuel Flush Tank. Corrosion Associated with Fluorination in the Oak Ridge National Laboratory Fluoride Volatility Process (Litman 1961) shows that this problem is significant. (2) Continued generation of Fluorine - Although the generation of Fluorine will be at a lower rate than experienced before the uranium removal, it will continue to be generated. This needs to be taken into consideration regardless of what actions are taken with the salt. (3) More than one phase of material - There are likely multiple phases of material in the salt (metal or compound), either suspended through the salt matrix, layered in the bottom of the tank, or both. These phases may contribute to plugging during any planned transfer. There is not enough data to know for sure. (4) Probe heat trace - The alternate transfer method does not include heat tracing of the bottom of the probe. There is a concern that this may cool the salt and other phases of materials present enough to block the flow of salt. (5) Stress-corrosion cracking - Additionally, there is a concern regarding moisture that may have been introduced into the tanks. Due to time constraints, this concern was not validated. However, if moisture was introduced into the tanks and not removed during heating the tanks before HF and F2 sparging, there would be an additional concern regarding the potential for stress-corrosion cracking of the tank walls.

TID.

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ISBN 13 :
Total Pages : 446 pages
Book Rating : 4.E/5 ( download)

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Book Synopsis TID. by :

Download or read book TID. written by and published by . This book was released on 1958 with total page 446 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Reactor Fuels, Materials and Systems under Extreme Environments

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Publisher : Frontiers Media SA
ISBN 13 : 2889747662
Total Pages : 360 pages
Book Rating : 4.8/5 (897 download)

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Book Synopsis Reactor Fuels, Materials and Systems under Extreme Environments by : Wenzhong Zhou

Download or read book Reactor Fuels, Materials and Systems under Extreme Environments written by Wenzhong Zhou and published by Frontiers Media SA. This book was released on 2022-03-25 with total page 360 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Nuclear Proliferation and Civilian Nuclear Power

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ISBN 13 :
Total Pages : 790 pages
Book Rating : 4.A/5 ( download)

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Book Synopsis Nuclear Proliferation and Civilian Nuclear Power by :

Download or read book Nuclear Proliferation and Civilian Nuclear Power written by and published by . This book was released on 1979 with total page 790 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Global Progress on Molten Salt Reactors

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Publisher : Elsevier
ISBN 13 : 032399377X
Total Pages : 294 pages
Book Rating : 4.3/5 (239 download)

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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

Publications, Reports, and Papers for 1961- from Oak Ridge National Laboratory

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ISBN 13 :
Total Pages : 256 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Publications, Reports, and Papers for 1961- from Oak Ridge National Laboratory by : Oak Ridge National Laboratory

Download or read book Publications, Reports, and Papers for 1961- from Oak Ridge National Laboratory written by Oak Ridge National Laboratory and published by . This book was released on 1961 with total page 256 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Scientific and Technical Aerospace Reports

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ISBN 13 :
Total Pages : 968 pages
Book Rating : 4.:/5 (31 download)

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Book Synopsis Scientific and Technical Aerospace Reports by :

Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1988 with total page 968 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Modeling the Molten Salt Reactor Experiment with the NEAMS System Analysis Module

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (15 download)

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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.

An Experimental Test Plan for the Characterization of Molten Salt Thermochemical Properties in Heat Transport Systems

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (727 download)

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Book Synopsis An Experimental Test Plan for the Characterization of Molten Salt Thermochemical Properties in Heat Transport Systems by :

Download or read book An Experimental Test Plan for the Characterization of Molten Salt Thermochemical Properties in Heat Transport Systems written by and published by . This book was released on 2010 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Molten salts are considered within the Very High Temperature Reactor program as heat transfer media because of their intrinsically favorable thermo-physical properties at temperatures starting from 300 C and extending up to 1200 C. In this context two main applications of molten salt are considered, both involving fluoride-based materials: as primary coolants for a heterogeneous fuel reactor core and as secondary heat transport medium to a helium power cycle for electricity generation or other processing plants, such as hydrogen production. The reference design concept here considered is the Advanced High Temperature Reactor (AHTR), which is a large passively safe reactor that uses solid graphite-matrix coated-particle fuel (similar to that used in gas-cooled reactors) and a molten salt primary and secondary coolant with peak temperatures between 700 and 1000 C, depending upon the application. However, the considerations included in this report apply to any high temperature system employing fluoride salts as heat transfer fluid, including intermediate heat exchangers for gas-cooled reactor concepts and homogenous molten salt concepts, and extending also to fast reactors, accelerator-driven systems and fusion energy systems. The purpose of this report is to identify the technical issues related to the thermo-physical and thermo-chemical properties of the molten salts that would require experimental characterization in order to proceed with a credible design of heat transfer systems and their subsequent safety evaluation and licensing. In particular, the report outlines an experimental R & D test plan that would have to be incorporated as part of the design and operation of an engineering scaled facility aimed at validating molten salt heat transfer components, such as Intermediate Heat Exchangers. This report builds on a previous review of thermo-physical properties and thermo-chemical characteristics of candidate molten salt coolants that was generated as part of the same project [1]. However, this work focuses on two materials: the LiF-BeF2 eutectic (67 and 33 mol%, respectively, also known as flibe) as primary coolant and the LiF-NaF-KF eutectic (46.5, 11.5, and 52 mol%, respectively, also known as flinak) as secondary heat transport fluid. At first common issues are identified, involving the preparation and purification of the materials as well as the development of suitable diagnostics. Than issues specific to each material and its application are considered, with focus on the compatibility with structural materials and the extension of the existing properties database.