The Metallurgy of Zirconium

The Metallurgy of Zirconium PDF Author: Benjamin Lustman
Publisher:
ISBN: 9781258715175
Category :
Languages : en
Pages : 794

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Book Description
Contributing Authors Include H. Etherington, R. C. Dalzell, D. W. Lillie And Others.

The Metallurgy of Zirconium

The Metallurgy of Zirconium PDF Author: Benjamin Lustman
Publisher:
ISBN: 9781258715175
Category :
Languages : en
Pages : 794

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Book Description
Contributing Authors Include H. Etherington, R. C. Dalzell, D. W. Lillie And Others.

Zirconium in Nuclear Applications

Zirconium in Nuclear Applications PDF Author: J. H. Schemel
Publisher: ASTM International
ISBN: 9780803107571
Category : Science
Languages : en
Pages : 544

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Book Description


Status of Fast Reactor Research and Technology Development

Status of Fast Reactor Research and Technology Development PDF Author: International Atomic Energy Agency
Publisher:
ISBN: 9781523130191
Category : Fast reactors
Languages : en
Pages : 0

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Book Description
"Based on a recommendation from the Technical Working Group on Fast Reactors, this publication is a regular update of previous publications on fast reactor technology. The publication provides comprehensive and detailed information on the technology of fast neutron reactors. The focus is on practical issues that are useful to engineers, scientists, managers, university students and professors. The main issues of discussion are experience in design, construction, operation and decommissioning, various areas of research and development, engineering, safety and national strategies, and public acceptance of fast reactors. In the summary the reader will find national strategies, international initiatives on innovative (i.e. Generation IV) systems and an assessment of public acceptance as related to fast reactors."--Résumé de l'éditeur.

Nuclear Fuel Safety Criteria

Nuclear Fuel Safety Criteria PDF Author: OECD Nuclear Energy Agency
Publisher: OECD Publishing
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 74

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Book Description
Presents brief descriptions of 20 fuel-related safety criteria along with both the rationale for having such criteria and possible new design and operational issues which could have an effect on them.

Zirconium in the Nuclear Industry

Zirconium in the Nuclear Industry PDF Author: George P. Sabol
Publisher: ASTM International
ISBN: 0803124066
Category : Nuclear fuel claddings
Languages : en
Pages : 907

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Advances in High Temperature Gas Cooled Reactor Fuel Technology

Advances in High Temperature Gas Cooled Reactor Fuel Technology PDF Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201253101
Category : Business & Economics
Languages : en
Pages : 639

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Book Description
This publication reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments. These comprise two specific benchmark exercises with the application of HTGR fuel performance and fission product release codes, which helped compare the quality and validity of the computer models against experimental data. The project participants also examined techniques for fuel characterization and advanced quality assessment/quality control. The key exercise included a round-robin experimental study on the measurements of fuel kernel and particle coating properties of recent Korean, South African and US coated particle productions applying the respective qualification measures of each participating Member State. The summary report documents the results and conclusions achieved by the project and underlines the added value to contemporary knowledge on HTGR fuel.

Zirconium in the Nuclear Industry

Zirconium in the Nuclear Industry PDF Author: Gerry D. Moan
Publisher: ASTM International
ISBN: 0803128959
Category : Nuclear fuel claddings
Languages : en
Pages : 891

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Book Description
Annotation The 41 papers of this proceedings volume were first presented at the 13th symposium on Zirconium in the Nuclear Industry held in Annecy, France in June of 2001. Many of the papers are devoted to material related issues, corrosion and hydriding behavior, in-reactor studies, and the behavior and properties of Zr alloys used in storing spent fuel. Some papers report on studies of second phase particles, irradiation creep and growth, and material performance during loss of coolant and reactivity initiated accidents. Annotation copyrighted by Book News, Inc., Portland, OR.

Progress Relating to Civilian Applications During ...

Progress Relating to Civilian Applications During ... PDF Author:
Publisher:
ISBN:
Category : Aluminum-uranium alloys
Languages : en
Pages : 102

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Book Description


Nuclear Waste Conditioning

Nuclear Waste Conditioning PDF Author: France. Commissariat à l'énergie atomique (CEA)
Publisher: Le Moniteur Editions
ISBN:
Category : Science
Languages : en
Pages : 160

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Applications-related Phenomena in Zirconium and Its Alloys

Applications-related Phenomena in Zirconium and Its Alloys PDF Author:
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 408

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Book Description