Zirconium in the Nuclear Industry: Tenth International Symposium

Zirconium in the Nuclear Industry: Tenth International Symposium PDF Author: A. M. Garde
Publisher: ASTM International
ISBN: 0803120117
Category : Nuclear fuel claddings
Languages : en
Pages : 805

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Zirconium in the Nuclear Industry: Tenth International Symposium

Zirconium in the Nuclear Industry: Tenth International Symposium PDF Author: A. M. Garde
Publisher: ASTM International
ISBN: 0803120117
Category : Nuclear fuel claddings
Languages : en
Pages : 805

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Reactor Core Materials

Reactor Core Materials PDF Author:
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 304

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Liquid Metal Cooled Reactors

Liquid Metal Cooled Reactors PDF Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201079077
Category : Liquid metal cooled reactors
Languages : en
Pages : 0

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Book Description
Presents a survey of worldwide experience gained with fast breeder reactor design, development and operation. Coverage includes state of the art of liquid metal fast reactor development; lead-bismuth cooled (LBC) ship reactor operation experience and LBC fast power reactor development; and treatment and disposal of spent sodium.

NAA-SR.

NAA-SR. PDF Author: U.S. Atomic Energy Commission
Publisher:
ISBN:
Category : Radiochemistry
Languages : en
Pages : 216

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Pellet-clad Interaction in Water Reactor Fuels

Pellet-clad Interaction in Water Reactor Fuels PDF Author:
Publisher: OECD Publishing
ISBN:
Category : Business & Economics
Languages : en
Pages : 562

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Book Description
This publication sets out the findings of an international seminar, held in Aix-en-Provence, France in March 2004, which considered recent progress in the field of pellet-clad interaction in light water reactor fuels. It also reviews current understanding of relevant phenomena and their impact on the nuclear fuel rod under the widest possible conditions, and about both uranium-oxide and mixed-oxide fuels.

Mars

Mars PDF Author: Viorel Badescu
Publisher: Springer Science & Business Media
ISBN: 3642036295
Category : Technology & Engineering
Languages : en
Pages : 716

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Book Description
th th Mars, the Red Planet, fourth planet from the Sun, forever linked with 19 and 20 Century fantasy of a bellicose, intelligent Martian civilization. The romance and excitement of that fiction remains today, even as technologically sophisticated - botic orbiters, landers, and rovers seek to unveil Mars’ secrets; but so far, they have yet to find evidence of life. The aura of excitement, though, is justified for another reason: Mars is a very special place. It is the only planetary surface in the Solar System where humans, once free from the bounds of Earth, might hope to establish habitable, self-sufficient colonies. Endowed with an insatiable drive, focused motivation, and a keen sense of - ploration and adventure, humans will undergo the extremes of physical hardship and danger to push the envelope, to do what has not yet been done. Because of their very nature, there is little doubt that humans will in fact conquer Mars. But even earth-bound extremes, such those experienced by the early polar explorers, may seem like a walk in the park compared to future experiences on Mars.

Viability of Inert Matrix Fuel in Reducing Plutonium Amounts in Reactors

Viability of Inert Matrix Fuel in Reducing Plutonium Amounts in Reactors PDF Author: International Atomic Energy Agency
Publisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 100

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Book Description
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.

Fluid Fuel Reactors

Fluid Fuel Reactors PDF Author: James A. Lane
Publisher:
ISBN:
Category : Fluid fuel reactors
Languages : en
Pages : 1016

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Status of Accelerator Driven Systems Research and Technology Development

Status of Accelerator Driven Systems Research and Technology Development PDF Author: International Atomic Energy Agency
Publisher: IAEA Tecdoc
ISBN: 9789201053152
Category : Science
Languages : en
Pages : 0

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Book Description
One of the greatest challenges for nuclear energy is how to properly manage the highly radioactive waste generated during irradiation in nuclear reactors. Accelerator Driven Systems (ADSs) may offer new prospects and advantages for the transmutation of such high level nuclear waste. ADS or accelerator driven transmutation of waste (ATW) consists of a high power proton accelerator, a heavy metal spallation target that produces neutrons when bombarded by the high power beam, and a sub-critical core that is neutronically coupled to the spallation target. This publication provides a comprehensive state of the art of the ADS technology by representing the different ADS concepts proposed worldwide in the last 15 years, as well as the related R&D activities and demonstration initiatives carried out at national international level.

Nuclear Fuel Elements

Nuclear Fuel Elements PDF Author: Brian R. T. Frost
Publisher: Elsevier
ISBN: 1483155250
Category : Technology & Engineering
Languages : en
Pages : 284

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Book Description
Nuclear Fuel Elements: Design, Fabrication and Performance is concerned with the design, fabrication, and performance of nuclear fuel elements, with emphasis on fast reactor fuel elements. Topics range from fuel types and the irradiation behavior of fuels to cladding and duct materials, fuel element design and modeling, fuel element performance testing and qualification, and the performance of water reactor fuels. Fast reactor fuel elements, research and test reactor fuel elements, and unconventional fuel elements are also covered. This volume consists of 12 chapters and begins with an overview of nuclear reactors and fuel elements, as well as fuel element design and development based on the reactor operator's approach, materials scientist's approach, and interdisciplinary approach. The reader is then introduced to different types of nuclear fuels and their irradiation behavior, considerations for using cladding and duct materials in fuel element design and development, and fuel element design and modeling. The chapters that follow focus on the testing of fuel element performance, experimental techniques and equipment for testing fuel element designs, and the performance of fuels for water reactors. Fuel elements for gas-cooled reactors, fast reactors, and research and test reactors are also described. The book concludes with an assessment of unconventional fuel elements. This book will be useful to fuel element technologists as well as materials scientists and engineers.