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Thoria-based Cermet Nuclear Fuel

Thoria-based Cermet Nuclear Fuel
Author:
Publisher:
Total Pages: 12
Release: 2002
Genre:
ISBN:

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Cermet nuclear fuel has been demonstrated to have significant potential to enhance fuel performance because of low internal fuel temperatures and low stored energy. The combination of these benefits with the inherent proliferation resistance, high burnup capability, and favorable neutronic properties of the thorium fuel cycle produces intriguing options for advanced nuclear fuel cycles. This paper describes aspects of a Nuclear Energy Research Initiative (NERI) project with two primary goals: (1) Evaluate the feasibility of implementing the thorium fuel cycle in existing or advanced reactors using a zirconium-matrix cermet fuel, and (2) Develop enabling technologies required for the economic application of this new fuel form. This paper will first describes the fuel thermal performance model developed for the analysis of dispersion metal matrix fuels. The model is then applied to the design and analysis of thorium/uranium/zirconium metal-matrix fuel pins for light-water reactors using neutronic simulation methods.


Thoria-based Cermet Nuclear Fuel

Thoria-based Cermet Nuclear Fuel
Author:
Publisher:
Total Pages: 10
Release: 2002
Genre:
ISBN:

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Cermet nuclear fuels have been demonstrated to have significant potential to enhance fuel performance because of low internal fuel temperatures and low stored energy. The combination of these benefits with the inherent proliferation resistance, high burnup capability, and favorable neutronic properties of the thorium fuel cycle produces intriguing options for advanced nuclear fuel cycles. This paper describes aspects of a Nuclear Energy Research Initiative (NERI) project with two primary goals: (1) evaluate the feasibility of implementing the thorium fuel cycle in existing or advanced reactors using a zirconium-matrix cermet fuel, and (2) develop enabling technologies required for the economic application of this new fuel form. Critical elements in the demonstration of this new fuel form include developing low-cost fabrication methods and characterizing the cermet properties and important performance parameters. A powder-in-tube drawing and heat treatment process is being evaluated as an alternative to hot extrusion. In this method, zirconium metal and ceramic microspheres are mixed, poured into a Zircaloy shell, and compacted into simulated fuel pins. Important processing variables being evaluated include the amount of compaction required to achieve a desired matrix density and the inter-drawing thermal treatment temperature required to achieve adequate matrix fusion and grain growth.


Thoria-based Cermet Nuclear Fuel

Thoria-based Cermet Nuclear Fuel
Author:
Publisher:
Total Pages: 8
Release: 2002
Genre:
ISBN:

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Cermet nuclear fuels have been demonstrated to have significant potential to enhance fuel performance because of low internal fuel temperatures and low stored energy. The combination of these benefits with the inherent proliferation resistance, high burnup capability, and favorable neutronic properties of the thorium fuel cycle produces intriguing options for advanced nuclear fuel cycles. This paper describes aspects of a Nuclear Energy Research Initiative (NERI) project with two primary goals: (1) Evaluate the feasibility of implementing the thorium fuel cycle in existing or advanced reactors using a zirconium-matrix cermet fuel, and (2) Develop enabling technologies required for the economic application of this new fuel form. Spray drying is a physical process of granulating fine powders that is used widely in the chemical, pharmaceutical, ceramic, and food industries. It is generally used to produce flowable fine powders. Occasionally it is used to fabricate sintered bodies like cemented carbides, but it has not, heretofore, been used to produce sintered microspheres. As a physical process, it can be adapted to many powder types and mixtures and thus, has appeal for nuclear fuels and waste forms of various compositions. It also permits easy recycling of process ''wastes'' and minimal chemical waste streams that can arise in chemical sol/gel processing. On the other hand, for radioactive powders, it presents safety challenges for processing these materials in powder form and in achieving microspheres of high density and perfection.


Thoria-based Nuclear Fuels

Thoria-based Nuclear Fuels
Author: Dasarathi Das
Publisher: Springer Science & Business Media
Total Pages: 423
Release: 2013-12-24
Genre: Technology & Engineering
ISBN: 1447155890

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This book presents the state of the art on thermophysical and thermochemical properties, fabrication methodologies, irradiation behaviours, fuel reprocessing procedures, and aspects of waste management for oxide fuels in general and for thoria-based fuels in particular. The book covers all the essential features involved in the development of and working with nuclear technology. With the help of key databases, many of which were created by the authors, information is presented in the form of tables, figures, schematic diagrams and flow sheets, and photographs. This information will be useful for scientists and engineers working in the nuclear field, particularly for design and simulation, and for establishing the technology. One special feature is the inclusion of the latest information on thoria-based fuels, especially on the use of thorium in power generation, as it has less proliferation potential for nuclear weapons. Given its natural abundance, thorium offers a future alternative to uranium fuels in nuclear technology. In closing, the latest information on conventional uranium and plutonium fuels is also provided.


Increasing Cermet Fuel Thermal Margin with Thoria for Nuclear Thermal Propulsion

Increasing Cermet Fuel Thermal Margin with Thoria for Nuclear Thermal Propulsion
Author: Gyutae Park
Publisher:
Total Pages: 0
Release: 2023
Genre:
ISBN:

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Nuclear thermal propulsion (NTP) technology was identified as an alternative for faster space travel over chemical combustion propulsion systems by NASA in its Design Reference Addendum 5.0. Potential improvements to NTP performance were considered by improving the fuel margin to melting point. A thorium-dioxide stabilized, high-assay low enriched uranium (HALEU) tungsten-uranium dioxide (W-UO2) CERMET fueled nuclear thermal propulsion (NTP) concept was produced based on the Space Capable Cryogenic Thermal Engine (SCCTE) reactor1. Axial fuel thoria fraction adjustments to improve the fuel thermal margin the reactor's specific impulse were studied using a one-dimensional axial thermohydraulic analysis of an equivalent annulus model of the average fuel coolant channel. Based on the one-dimensional analysis, fuel composition was adjusted leading to a fuel mass decrease of 5.45 kilograms, excess-reactivity reduction of 962 pcm, and an increased fuel margin to melting point of 740 K for the average fuel. Finally, a three-dimensional computational fluid dynamics (CFD) model of the hottest fuel pin of the base and adjusted designs with neutronics-informed three-dimensional fuel heating rates were compared. The CFD analysis predicted fuel melting in the hottest pin of both designs, identifying the potential need for additional design adjustment outside of fuel composition. The suggested changes reduced the total melting volume by 10 percent. Thus, temperature-informed adjustment of fuel thoria fraction offered improvements in fuel melting point.


Thorium and the Third Fuel

Thorium and the Third Fuel
Author: Joseph M. Dukert
Publisher:
Total Pages: 52
Release: 1970
Genre: Thorium
ISBN:

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Thorium Fuel Cycle

Thorium Fuel Cycle
Author: International Atomic Energy Agency
Publisher:
Total Pages: 120
Release: 2005
Genre: Business & Economics
ISBN:

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Provides a critical review of the thorium fuel cycle: potential benefits and challenges in the thorium fuel cycle, mainly based on the latest developments at the front end of the fuel cycle, applying thorium fuel cycle options, and at the back end of the thorium fuel cycle.


Thorium Fuel Cycle

Thorium Fuel Cycle
Author: Raymond G. Wymer
Publisher:
Total Pages: 870
Release: 1968
Genre: Science
ISBN:

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Thorium Energy for the World

Thorium Energy for the World
Author: Jean-Pierre Revol
Publisher: Springer
Total Pages: 442
Release: 2016-04-05
Genre: Science
ISBN: 3319265423

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The Thorium Energy Conference (ThEC13) gathered some of the world’s leading experts on thorium technologies to review the possibility of destroying nuclear waste in the short term, and replacing the uranium fuel cycle in nuclear systems with the thorium fuel cycle in the long term. The latter would provide abundant, reliable and safe energy with no CO2 production, no air pollution, and minimal waste production. The participants, representatives of 30 countries, included Carlo Rubbia, Nobel Prize Laureate in physics and inventor of the Energy Amplifier; Jack Steinberger, Nobel Prize Laureate in physics; Hans Blix, former Director General of the International Atomic Energy Agency (IAEA); Rolf Heuer, Director General of CERN; Pascal Couchepin, former President of the Swiss Confederation; and Claude Haegi, President of the FEDRE, to name just a few. The ThEC13 proceedings are a source of reference on the use of thorium for energy generation. They offer detailed technical reviews of the status of thorium energy technologies, from basic R&D to industrial developments. They also describe how thorium can be used in critical reactors and in subcritical accelerator-driven systems (ADS), answering the important questions: – Why is thorium so attractive and what is the role of innovation, in particular in the nuclear energy domain? – What are the national and international R&D programs on thorium technologies and how are they progressing? ThEC13 was organized jointly by the international Thorium Energy Committee (iThEC), an association based in Geneva, and the International Thorium Energy Organisation (IThEO). It was held in the Globe of Science and Innovation at the European Organization for Nuclear Research (CERN), Geneva, Switzerland, in October 2013.