Advances in Nuclear Science and Technology

Contributors

Preface

Contents of Previous Volumes

Quasi-Exponential Decay of Neutron Fields

I. Introduction

II. Exponential and Quasi-Exponential Behavior

III. Experiments

IV. Theory

V. Epilogue

References

Evaluation of Integral Physics Experiments in Fast Zero Power Facilities

I. Introduction

II. Accuracy of Nuclear Data Used for Reactor Calculations

III. Implications of Nuclear Data Uncertainties

IV. Role of Integral Experiments in Improving the Nuclear Data Basis

V. Status of Evaluation Efforts

VI. Summary and Future Aspects

References

Evaluated Nuclear Data Files

I. Introduction

II. Description of Evaluated Nuclear Data Files

III. Procedures for Data Evaluation

Appendix A: Formats for Evaluated Nuclear Data Libraries

Appendix B: Checking Procedures for Evaluated Data Files

References

The Management of Fission Product and Long-Lived Alpha Wastes

I. Introduction

II. Magnitude of the Problem

III. Current Situation: Practices, Experience, and General Planning

IV. Solidification Techniques and Final Product Characteristics

V. Storage, Disposal, and Transportation of the Solidified Waste

VI. Economic Considerations

VII. Conclusions

References

Finite Element Methods in Reactor Physics Analysis

I. Introduction

II. Piecewise Polynomial Spaces

III. Neutron Spectrum Calculations

IV. Static Diffusion Problems

V. Time-Dependent Problems

VI. Summary

Appendix—Nomenclature

References

Coated Nuclear Fuel Particles

I. Introduction

II. High-Temperature Reactors

III. The Fuel

IV. Pyrolytic Carbon Coated Particles

V. Pyrolytic Carbon

VI. Silicon Carbide

VII. Mathematical Models

VIII. Production Equipment

IX. Coating Characteristics According to the Deposition Conditions

X. Analysis and Control of the Finished Particles

XI. Irradiation Tests

References

Subject Index