Advances in Nuclear Science and Technology: Festschrift in Honor of Eugene P. Wigner

Author:   Jeffery Lewins
Publisher:   Springer Science+Business Media
Edition:   1987 ed.
Volume:   19
ISBN:  

9780306425431


Pages:   490
Publication Date:   01 June 1987
Format:   Hardback
Availability:   Out of stock   Availability explained
The supplier is temporarily out of stock of this item. It will be ordered for you on backorder and shipped when it becomes available.

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Advances in Nuclear Science and Technology: Festschrift in Honor of Eugene P. Wigner


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Author:   Jeffery Lewins
Publisher:   Springer Science+Business Media
Imprint:   Kluwer Academic/Plenum Publishers
Edition:   1987 ed.
Volume:   19
Weight:   0.870kg
ISBN:  

9780306425431


ISBN 10:   0306425432
Pages:   490
Publication Date:   01 June 1987
Audience:   College/higher education ,  Professional and scholarly ,  Undergraduate ,  Postgraduate, Research & Scholarly
Format:   Hardback
Publisher's Status:   Active
Availability:   Out of stock   Availability explained
The supplier is temporarily out of stock of this item. It will be ordered for you on backorder and shipped when it becomes available.

Table of Contents

Eugene Wigner and Nuclear Energy.- I. Introduction.- II. The Pre-Chicago Days.- III. Chicago Metallurgical Laboratory.- IV. Clinton Laboratories, 1946–47.- V. Reactor Physics and General Engineering.- VI. Macroscopic Reactor Theory.- VII. Temperature Effects: The Wigner-Wilkins Distribution.- VIII.Solid State Physics.- IX. Nuclear Physics at Chicago and Clinton.- X. General Energy Policy.- XI. Civil Defence.- XII. Wigner and the Founding of ORNL.- XIII.Eugene Wigner and Nuclear Energy.- XIV. Annotated Bibliographies.- The PIUS Principle and the SECURE Reactor Concepts.- I. Introduction.- II. Design Goals for “Forgiving” LWRs.- III. The PIUS Design Principle.- IV. System Modelling.- V. Design Implementation.- VI. The Nuclear Power Reactor SECURE-P.- VII. The Heat Producing Reactor SECURE-H.- VIII.The Low Temperature Heating Reactor SECURE-LH.- IX. Concluding Remarks.- PRISM: An Innovative Inherently Safe Modular Sodium Cooled Breeder Reactor.- I. Introduction.- II. Overall Plant Description.- III. Reactor Assembly and Support Structures.- IV. Heat Transport and Power Generation Systems.- V. Shutdown Heat Removal Systems.- VI. PRISM Inherent Safety Characteristics.- VII. Concept Summary and Implementation Strategy.- Generalised Perturbation Theory (GPT). A Heuristic Approach.- I. Introduction.- II. GPT Methodology for Linear Systems.- III. GPT Methodology for Nonlinear Systems.- IV. Fields of Interest.- V. Expansion of the Perturbed Field Function.- VI. Final Remarks.- Some Recent Developments in Finite Element Methods for Neutron Transport Theory.- I. Introduction.- II. Forms of the Transport Equation.- III. Approximate Solution Methods.- IV. A Unified Treatment.- V. Application of the Finite Element Method.- VI. Three Design Codes Illustrated.- VII. CompositeSolutions.- VIII.Future Trends.

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