Advances in Nuclear Science and Technology, Volume 5 presents the underlying principles and theory, as well as the practical applications of the advances in the nuclear field. This book reviews the specialized applications to such fields as space propulsion.Organized into six chapters, this volume begins with an overview of the design and objective of the Fast Flux Test Facility to provide fast flux irradiation testing facilities. This text then examines the problem in the design of nuclear reactors, which is the analysis of the spatial and temporal behavior of the neutron and temperature distributions within the system. Other chapters consider the three major ways of estimating shield effectiveness. This book discusses as well the purpose of variational principle, which is a characterization of a function as the stationary point of an appropriate functional. The final chapter deals with the solution of the Boltzmann transport equation.This book is a valuable resource for engineers.

ContributorsPrefaceContents of Previous VolumesObjectives and Design of the Fast Flux Facility I. Introduction II. Objectives of the FFTF III. FTR Nuclear Design Aspects IV. FTR Mechanical Design Aspects V. Fuel and Test Element Handling VI. Present Status and Future Programs ReferencesStability Analysis of Nonlinear Space Dependent Reactor Kinetics I. Introduction II. The Space-Time Kinetics Equations III. Notation, Definitions, and Preliminaries IV. Mathematical Considerations V. Stability Techniques for Distributed Parameter Systems VI. Examples and Applications to Various Feedback Models VII. Conclusions ReferencesMethods and Data for Reactor Shield Calculations I. Introduction II. Spherical Harmonics Expansion and Related Methods III. Discrete Ordinates (SN) IV. Removal Cross Section V. Transport-Slowing Down VI. Multigroups Calculations VII. The Moments Method VIII. Gamma-Ray Buildup Factors IX. Neutron Attenuation Curves for Fission Sources X. Geometric Transformations XI. Monte Carlo XII. Albedo XIII. Ducts and Voids XIV. Secondary Gamma-Ray Dose ReferencesVariational Methods in Nuclear Engineering I. Introduction II. What Is a Variational Principle? III. The Equations of Euler IV. Finding the Variational Problem V. Variational Problems with Constraints VI. The Method of Lewins and Pomraning VII. Rayleigh-Ritz and Weighted Residual Methods VIII. Discontinuous Approximations IX. Extending the Domain X. Canonical and Involutory Transformations of Variational Problems XI. Bellman's Approach XII. Transformation of Problems with Many Operators XIII. Discussion XIV. Extension of Canonical Principles-Use in Deriving Difference Equations XV. Conclusion ReferencesNuclear Power for Space Applications I. Introduction II. Principal Isotope Systems III. Principal Reactor Systems IV. Other Systems V. Radiators VI. Concluding Remarks ReferencesA Round-Off Free Solution of the Boltzmann Transport Equation in Slab Geometry I. Introduction II. A Brief Survey of Methods Employed for the Solution of the Transport Equation in Slab Geometry III. Transformation of the Monoenergetic Transport Equation IV. An Example of Round-Off Error V. A Round-Off Free Solution for the Monoenergetic One-Velocity Single-Region Transport Equation VI. The Monoenergetic Distributed Source Problem VII. The Multiregion Solution of the Slab Problem VIII. Energy Dependence : The Slowing Down IX. Applications of the Round-Off Free Solution Appendix A Appendix B. The Inverse of (MW) ReferencesAuthor IndexSubject Index