Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1372

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Book Description

Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1372

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Book Description


Thorium Fuel Cycle

Thorium Fuel Cycle PDF Author: International Atomic Energy Agency
Publisher:
ISBN:
Category : Business & Economics
Languages : en
Pages : 120

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Book Description
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.

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.

Canada Enters the Nuclear Age

Canada Enters the Nuclear Age PDF Author: Atomic Energy of Canada Limited
Publisher: McGill-Queen's Press - MQUP
ISBN: 9780773516014
Category : Business & Economics
Languages : en
Pages : 466

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Book Description
The nuclear energy company has overseen the production of its own history, focusing on programs at its laboratories in Chalk River, Ontario, and Whiteshell, Manitoba between 1943 and 1985. The 16 scientists who wrote the narrative discuss the organization and operations of the laboratories, nuclear safety and radiation protection, radioisotopes, basic research, developing the CANDU reactor, managing the radioactive wastes, business development, and revenue generation. Canadian card order number: C97-900188-9. Annotation copyrighted by Book News, Inc., Portland, OR

An Introduction to Radiation Protection

An Introduction to Radiation Protection PDF Author: ALAN MARTIN and SAMUEL A. HARBISON
Publisher: Springer
ISBN: 1489969403
Category : Technology & Engineering
Languages : en
Pages : 253

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Book Description


Water Reactor Fuel Element Performance Computer Modelling

Water Reactor Fuel Element Performance Computer Modelling PDF Author: John Gittus
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 736

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Book Description


Guide to Nuclear Power Cost Evaluation: Equipment costs

Guide to Nuclear Power Cost Evaluation: Equipment costs PDF Author: Kaiser Engineers
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 140

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Book Description


Decommissioning of Nuclear Facilities

Decommissioning of Nuclear Facilities PDF Author: OECD Nuclear Energy Agency
Publisher: Nuclear Energy Agency, Organisation for Economic Co-operation and Development ; Washington, D.C. : OECD Publications and Information Centre
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 142

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Book Description


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.