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Book Dispersion Fuel Elements

Download or read book Dispersion Fuel Elements written by Abe Noel Holden and published by . This book was released on 1967 with total page 276 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Dispersion Fuels for Advanced Organic Moderated Reactor

Download or read book Dispersion Fuels for Advanced Organic Moderated Reactor written by J. Kroehler and published by . This book was released on 1960 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Alloy Dispersion Fuel Elements

Download or read book Alloy Dispersion Fuel Elements written by J. Paul Pemsler and published by . This book was released on 1959 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book EK 10 Dispersion Fuel Elements for Experimental and University Reactors

Download or read book EK 10 Dispersion Fuel Elements for Experimental and University Reactors written by Władysław Rutkowski and published by . This book was released on 1965 with total page 26 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Nuclear Regulatory Commission Issuances

Download or read book Nuclear Regulatory Commission Issuances written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1982 with total page 774 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Dispersion Type Fuel Elements for Nuclear Reactors

Download or read book Dispersion Type Fuel Elements for Nuclear Reactors written by Andreĭ Grigorʹevich Samoĭlov and published by . This book was released on 1970 with total page 147 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Dispersion Fuel Elements

Download or read book Dispersion Fuel Elements written by and published by . This book was released on 1967 with total page 255 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Cladding and Dispersion Fuel Development at ORNL

Download or read book Cladding and Dispersion Fuel Development at ORNL written by and published by . This book was released on 1967 with total page 29 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Structural Materials for Generation IV Nuclear Reactors

Download or read book Structural Materials for Generation IV Nuclear Reactors written by Pascal Yvon and published by Woodhead Publishing. This book was released on 2016-08-27 with total page 686 pages. Available in PDF, EPUB and Kindle. Book excerpt: Operating at a high level of fuel efficiency, safety, proliferation-resistance, sustainability and cost, generation IV nuclear reactors promise enhanced features to an energy resource which is already seen as an outstanding source of reliable base load power. The performance and reliability of materials when subjected to the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors are essential areas of study, as key considerations for the successful development of generation IV reactors are suitable structural materials for both in-core and out-of-core applications. Structural Materials for Generation IV Nuclear Reactors explores the current state-of-the art in these areas. Part One reviews the materials, requirements and challenges in generation IV systems. Part Two presents the core materials with chapters on irradiation resistant austenitic steels, ODS/FM steels and refractory metals amongst others. Part Three looks at out-of-core materials. Structural Materials for Generation IV Nuclear Reactors is an essential reference text for professional scientists, engineers and postgraduate researchers involved in the development of generation IV nuclear reactors. Introduces the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors and implications for structural materials Contains chapters on the key core and out-of-core materials, from steels to advanced micro-laminates Written by an expert in that particular area

Book Viability of Inert Matrix Fuel in Reducing Plutonium Amounts in Reactors

Download or read book Viability of Inert Matrix Fuel in Reducing Plutonium Amounts in Reactors written by International Atomic Energy Agency and published by IAEA. This book was released on 2006 with total page 100 pages. Available in PDF, EPUB and Kindle. Book excerpt: The reactors around the world have produced more than 2000 tonnes of plutonium, contained in spent fuel or as separated forms through reprocessing. Disposition of fissile materials has become a primary concern of nuclear non-proliferation efforts worldwide. There is a significant interest in IAEA Member States to develop proliferation resistant nuclear fuel cycles for incineration of plutonium such as inert matrix fuels (IMFs). This publication reviews the status of potential IMF candidates and describes several identified candidate materials for both fast and thermal reactors: MgO, ZrO2, SiC, Zr alloy, SiAl, ZrN; some of these have undergone test irradiations and post irradiation examination. Also discussed are modelling of IMF fuel performance and safety analysis. System studies have identified strategies for both implementation of IMF fuel as homogeneous or heterogeneous phases, as assemblies or core loadings and in existing reactors in the shorter term, as well as in new reactors in the longer term.

Book Dispersion fuel Nuclear Reactor Elements

Download or read book Dispersion fuel Nuclear Reactor Elements written by A. G. Samoilov and published by . This book was released on 1968 with total page 223 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Dispersion fuel Nuclear Reactor Elements

Download or read book Dispersion fuel Nuclear Reactor Elements written by Андрей Григорьевич Самойлов and published by . This book was released on 1968 with total page 240 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Properties of Uranium Dioxide stainless Steel Dispersion Fuel Plates

Download or read book Properties of Uranium Dioxide stainless Steel Dispersion Fuel Plates written by Stan J. Paprocki and published by . This book was released on 1959 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt: The physical and mechanical properties of GCRE-type fuel elements were determined from room temperature to 1650 deg F. The fuel elements were prepared by cladding Type 318 stainless steel sheet to a core containing 15 to 35 wt.% UO/ sub 2/ in either prealloyed Type 318 stainless steel or elemental iron-18 wt.% chromium-14 wt. % nickel-2.5 wt. % molybdenum. The tensile strength in the direction perpendicular to the rolling plane decreased from 24,600 psi at room temperature to 9,200 psi at 1650 deg F for the reference fuel plate, whose core contained 25 wt.% UO2 in the elemental alloy. The tensile strength in the longitudinal direction for this fuel element ranged from 54,800 psi at room temperature to 14,200 psi at 1650 deg F, with elongation in 2 in. ranging from 8 to 13 per cent. The extrapolated stress for 1000hr rupture life at 1650 deg F was 1800 psi, and a 1.4T bend was withstood without cracking. The mean linear thermal coefficient of expansion was 11.0 x 10−6 per deg F for the range 68 to 1700 deg F. (auth).

Book Irradiation Behavior of Dispersion Fuels

Download or read book Irradiation Behavior of Dispersion Fuels written by D. W. White (Jr.) and published by . This book was released on 1957 with total page 62 pages. Available in PDF, EPUB and Kindle. Book excerpt: