Nuclear Science Abstracts PDF Download
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Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 658
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Book Description
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 658
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Book Description
Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 406
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Book Description
Author: Mordecai Avriel
Publisher: Courier Corporation
ISBN: 9780486432274
Category : Mathematics
Languages : en
Pages : 548
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Book Description
This overview provides a single-volume treatment of key algorithms and theories. Begins with the derivation of optimality conditions and discussions of convex programming, duality, generalized convexity, and analysis of selected nonlinear programs, and then explores techniques for numerical solutions and unconstrained optimization methods. 1976 edition. Includes 58 figures and 7 tables.
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1036
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Book Description
Author:
Publisher:
ISBN:
Category : Energy development
Languages : en
Pages : 176
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Book Description
Author:
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ISBN:
Category : Aluminum-uranium alloys
Languages : en
Pages : 74
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Book Description
Author:
Publisher:
ISBN:
Category : Electronic journals
Languages : en
Pages : 1088
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Book Description
Includes English language abstracts from Japanese articles in Nihon Genshiryoku Gakkai Shi (Journal of the Atomic Energy Society of Japan).
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 442
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Book Description
Author:
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 96
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Book Description
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.
