The technology of micro heat pipe cooled reactor: A review
TL;DR: In this paper, the development and technologies of micro heat pipe cooled reactor are overviewed, and difficulties and challenges need to be overcome in the future, including heat pipe cascading failure, fuel enrichment, structure integrity, machining, monolithic thermal stress, inspection and qualification, etc.
About: This article is published in Annals of Nuclear Energy.The article was published on 2020-01-01. It has received 88 citations till now. The article focuses on the topics: Nuclear reactor core & Heat pipe.
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TL;DR: In this paper, the authors present a survey of nuclear power development, nuclear waste disposal, storage and disposal of nuclear wastes, nuclear Reactor safety, and future nuclear Reactors.
Abstract: Contents: 1. Nuclear Power Development. 2. Natural Radioactivity and Radiation Exposures. 3. Neutron Reactions. 4. Nuclear Fission. 5. Chain Reaction and Nuclear Reactors. 6. Types of Nuclear Reactors. 7. Nuclear Fuel Cycle. 8. Nuclear Waste Disposal: Magnitudes of Waste. 9. Storage and Disposal of Nuclear Wastes. 10. Administrative and Policy Issues in Nuclear Waste Disposal. 11. Nuclear Reactor Safety. 12. Nuclear Reactor Accidents. 13. Reactor Safety and Future Nuclear Reactors. 14. Nuclear Energy and Weapons Proliferation. 15. Costs of Electricity from Nuclear Power. 16. The Prospects for Nuclear Power. Appendices.
159 citations
01 Dec 2020
TL;DR: The promise of SMRs as means to reduce greenhouse gas emissions and their ability to supply reliable and base-load power, the licensing of such reactors by national regulators will provide a boost to their acceptability and adaptability as a player in combating climate change.
Abstract: This paper reviews the smallness, modularity and reactor-design aspects of emerging small modular reactors (SMRs). It is shown that small (whether in physical size or power level) reactors are not new, but offer economic and flexibility advantages that allow their use in a variety of applications. The different definitions of modularity are reviewed, including modularity in design, process intensification, manufacturing and construction. It is shown that these forms of modularity when applied to SMRs have some advantages, but also have some challenges that need to be addressed if their full potential is to be realized. Even if these forms of modularity are not fully utilized, the lower power ( ≤ 300 MW electrical) of SMRs allows the formation of larger power plants by incremental addition of reactor units, in the so-called scale modularity. The paper reviews the unique features of emerging SMR designs, and compares them to those of the early era of nuclear power. It is shown that while many modern SMR designs incorporate well-proven features that were tested and proven in early reactors. others introduce aspects of Generation IV reactors, in terms of inherent and/or passive safety. Given the promise of SMRs as means to reduce greenhouse gas emissions and their ability to supply reliable and base-load power, the licensing of such reactors by national regulators will provide a boost to their acceptability and adaptability as a player in combating climate change.
43 citations
TL;DR: In this article, the authors developed a code for studying the operating thermal-hydraulic characteristics of the reactor core, which consists of core thermal hydraulic model, neutron kinetics model and heat pipe startup model.
40 citations
TL;DR: In this paper, the impact of various techniques on thermal performance of heat pipes and their impact level and constraints such as optimized parameters, manufacturing constraints, economic feasibility and commercial barriers are reviewed and discussed.
Abstract: The aim of this study is to oversee the impact of various techniques on thermal performance of heat pipes and to comprehensively cover the progress made so far in improving thermal performance. Thermal performance of heat pipes has been considerably improved by applying very novel techniques proposed by different investigators. Some major techniques have been reviewed and discussed: use of nanofluids, manufacturing different types of grooves and fins, use of different types of wicks, by inner surface treatment, use of self-rewetting fluids, use of embedded heat pipes that is passive cooling mechanism, using various inclination angles in heat pipes, etc. The presented study concludes that there are diverse methods for thermal performance enhancement of heat pipes each having its own impact level and constraints such as optimized parameters, manufacturing constraints, economic feasibility and commercial barriers. Some techniques show reversion in results when exceeded a certain level, e.g., crossing optimum concentration of nanofluid would reduce thermal performance of heat pipes. This review yields enough knowledge to optimize alteration parameters to get maximum augmentation in results and provides strong insight to decide about, which specific technique should be used for a case.
39 citations
TL;DR: In this paper, the authors used the Monte Carlo program RMC and the commercial finite element program ANSYS Mechanical to develop coupled solutions of the neutronic (N), thermal (T), and mechanical (M) effects in a heat pipe cooled reactor.
28 citations
References
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Book•
01 Jan 1989
TL;DR: The first law of thermodynamics -closed systems, control volumes, and the second law of entropy -a measure of disorder energy -are the properties of pure substances of high-speed fluid flow as mentioned in this paper.
Abstract: Basic concepts of thermodynamics properties of pure substances the first law of thermodynamics - closed systems, control volumes the second law of thermodynamics entropy - a measure of disorder energy - a measure of work potential gas power cycles vapour and combined power cycles refrigeration cycles thermodynamics property gas mixtures gas vapour mixtures and air conditioning chemical reactions chemical and phase equilibrium thermodynamics of high-speed fluid flow property tables and charts (SI units, English units) about the software
4,495 citations
Book•
01 Mar 1995
TL;DR: In this article, the authors present a detailed analysis of non-conventional heat pipe properties, including variable conductance heat pipes, and their properties in terms of heat transfer and mass transfer.
Abstract: Preface Nomenclature 1.Introduction 2.Solid-Liquid-Vapor Phenomena, Driving Forces and Interfacial Heat and Mass Transfer 3.Steady Hydrodynamic and Thermal Characteristics 4.Heat Transfer Limitations 5.Continuum Transient and Frozen Startup Behavior of Heat Pipes 6.Two-Phase Closed Thermosyphons 7.Rotating and Revolving Heat Pipes 8.Variable Conductance Heat Pipes 9.Capillary Pumped Loop and Loop Heat Pipe Systems 10.Micro/Miniature Heat Pipe Characteristics and Operating Limitations 11.Heat Pipe Heat Exchangers 12.Analysis of Nonconventional Heat Pipes 13.Special Effects on Heat Pipes 14.Heat Pipe Fabrication, Processing, and Testing Appendix A:Thermophysical Properties Appedix B:Experimental Heat Pipe Results Index
1,516 citations
Book•
01 Jan 1975
TL;DR: In this article, the authors present a comprehensive overview of nuclear physics and its application in the field of nuclear power plants, including the following: 1. Atomic and Nuclear Physics. 2. Nuclear Models. 3. Nuclear Reactors and Nuclear Power Plants.
Abstract: (Most chapters end with References and Problems). 1. Nuclear Engineering. 2. Atomic and Nuclear Physics. Fundamental Particles. Atomic and Nuclear Structure. Atomic and Molecular Weight. Atomic and Nuclear Radii. Mass and Energy. Particle Wavelengths. Excited States and Radiation. Nuclear Stability and Radioactive Decay. Radioactivity Calculations. Nuclear Reactions. Binding Energy. Nuclear Models. Gases, Liquids, and Solids. Atom Density. 3. Interaction of Radiation with Matter. Neutron Interactions. Cross-Sections. Neutron Attenuation. Neutron Flux. Neutron Cross-Section Data. Energy Loss in Scattering Collisions. Fission. y-Ray Interactions with Matter. Charged Particles. 4. Nuclear Reactors and Nuclear Power. The Fission Chain Reaction. Nuclear Reactor Fuels. Non-Nuclear Components of Nuclear Power Plants. Components of Nuclear Reactors. Power Reactors and Nuclear Steam Supply Systems. Nuclear Cycles. Isotope Separation. Fuel Reprocessing. Radioactive Waste Disposal. 5. Neutron Diffusion and Moderation. Neutron Flux. Fick's Law. The Equation of Continuity. The Diffusion Equation. Boundary Conditions. Solutions of the Diffusion Equation. The Diffusion Length. The Group-Diffusion Method. Thermal Neutron Diffusion. Two-Group Calculation of Neutron Moderation. 6. Nuclear Reactor Theory. One-Group Reactor Equation. The Slab Reactor. Other Reactor Shapes. The One-Group Critical Equation. Thermal Reactors. Reflected Reactors. Multigroup Calculations. Heterogeneous Reactors. 7. The Time-Dependent Reactor. Classification of Time Problems. Reactor Kinetics. Control Rods and Chemical Shim. Temperature Effects on Reactivity. Fission Product Poisoning. Core Properties during Lifetime. 8. Heat Removal from Nuclear Reactors. General Thermodynamic Considerations. Heat Generation in Reactors. Heat Flow by Conduction. Heat Transfer to Coolants. Boiling Heat Transfer. Thermal Design of a Reactor. 9. Radiation Protection. History of Radiation Effects. Radiation Units. Some Elementary Biology. The Biological Effects of Radiation. Quantitative Effects of Radiation on the Human Species. Calculations of Radiation Effects. Natural and Man-Made Radiation Sources. Standards of Radiation Protection. Computations of Exposure and Dose. Standards for Intake of Radionuclides. Exposure from y-Ray Sources. Glossary. 10. Radiation Shielding. Gamma-Ray Shielding: Buildup Factors. Infinite Planar and Disc Sources. The Line Source. Internal Sources. Multilayered Shields. Nuclear Reactor Shielding: Principles of Reactor Shielding. Removal Cross-Sections. The Reactor Shield Design: Removal-Attenuation Calculatons. The Removal-Diffusion Method. Exact Methods. Shielding y-Rays. Coolant Activation. Ducts in Shields. 11. Reactor Licensing, Safety, and the Environment. Governmental Authority and Responsibility. Reactor Licensing. Principles of Nuclear Power Plant Safety. Dispersion of Effluents from Nuclear Facilities. Radiation Doses from Nuclear Plants. Reactor Siting. Reactor Accidents. Accident Risk Analysis. Environmental Radiation Doses. Appendixes. I. Units and Conversion Factors. II. Fundamental Constants and Data. III. Vector Operations in Orthogonal Curvilinear Coordinates. IV. Thermodynamic and Physical Properties. V. Bessel Functions. Index.
730 citations
Book•
12 Oct 2006
TL;DR: The Heat Pipes 6th Edition as discussed by the authors is an essential guide for practicing engineers and an ideal text for postgraduate students, taking a highly practical approach to the design and selection of heat pipes.
Abstract: Heat Pipes 6th Edition, is an essential guide for practicing engineers and an ideal text for postgraduate students. This book takes a highly practical approach to the design and selection of heat pipes. This new edition has been updated with new information on the underlying theory of heat pipes and heat transfer, fully updated applications, new data sections, updated chapters on design and on electronics cooling applications. Reay's book is a useful reference as well as an accessible introduction for those approaching the topic for the first time. It contains all information required to design and manufacture a heat pipe. It is suitable for use as a professional reference and graduate text. It is revised with greater coverage of key electronic cooling applications.
510 citations