Advances in Nuclear Science and Technology

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.