Download e-book for iPad: Corrosion in the Nuclear Industry by Prepared by the Working Party on Nuclear Corrosion

By Prepared by the Working Party on Nuclear Corrosion

ISBN-10: 090146273X

ISBN-13: 9780901462732

ISBN-10: 1601191693

ISBN-13: 9781601191694

This quantity makes a speciality of 9 themes of relevance to the nuclear strength undefined. Chapters disguise: pressurised water reactors, boiling water reactors, gasoline components, complicated fuel reactors, extreme temperature reactors, liquid steel quickly breeders, fusion reactors, reprocessing and waste administration.
Content:
• entrance topic
• desk of Contents
• ecu Federation of Corrosion - sequence advent
• creation
1. Corrosion in Pressurized Water Reactors
2. Corrosion difficulties in Boiling Water Reactors and their treatments
three. Zircaloy gas Cladding Corrosion Behaviour lower than gentle Water Reactor Operation and twist of fate stipulations
four. The Oxidation of based Stainless Steels and gasoline Cladding within the complicated Gas-Cooled Reactors
five. Corrosion Behaviour of metal fabrics within the Cooling fuel of extreme temperature Reactors
6. Corrosion in speedy Breeder Reactors
7. Corrosion difficulties in Nuclear Fusion Reactors
eight. Corrosion Resistance of steel fabrics to be used in Nuclear gas Reprocessing
nine. Corrosion elements of packing containers for High-Level Waste Disposal

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Extra resources for Corrosion in the Nuclear Industry

Sample text

Brandis, B. Huchtemann, P. Schuler, H. Weber, W. Nickel: Proc. I n t . Conf. on Creep, April 14-17, Tokyo 1986, p. Quadakkers: Materials Science and Engineering 87 (1987) 107 ACKNOWLEDGEMENTS The investigations presented have been carried out f o r the German HTGR project PNP i n cooperation w i t h the i n d u s t r i a l project partners and subcontractors under the sponsorship of the Minister fiir Wirtschaft, Mittelstand und Verkehr des Landes Nordrhein-Westfalen and the Bundesminister fiir Forschung und Technologic.

E temperature gradient in the system flow velocity. Of course, some of these parameters, especially the last two, depend on the use of the liquid metal. If it is used only as a tritium breeder, it can be semi-stagnant and thus with only small temperature gradients in the system. If it is also used as a coolant, high flow velocities and l a r g e O T will be present, with an jncrease in the mass transfer problems. 2. Lithium It is only during a limited number of years that litliium compatibility studies have been directed towards experimental conditions corresponding to the requirements of the fusion reactor conceptual designs.

Pulham, ibid. Vol. 3, p. 99 34. G. Barker, V. A. Lees, H. Kolbe, L. Orecchia and T. Sample, to be published in J. of Nucl. Mat. 35. Orecchia, to be published in J. of Nucl. Mat. 36. Saunier, Personal Communication, work to be published in J . of Nucl. Mat. 37. Sano, J. Nucl. Mat. 80 (1979), 8. G. A. R. Moore, Material Behaviour & Physical Chemistry in Liq. Metal Systems, Ed. U. Y. 113 9. E. Ruedl, V. Kolbe, J. Nucl. Mat. 110 (1982), 28 10. E. Ruedl, T. Sasaki, J. Nucl. Mat. 116 (19831, 112 11. E.

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Corrosion in the Nuclear Industry by Prepared by the Working Party on Nuclear Corrosion


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