Advances in Nuclear Science and Technology
Published on 9. May 2013
Book
Paperback/Softback
X, 565 pages
978-1-4613-2864-3 (ISBN)
Description
The present volume in our annual review series reviews a wide range of developments, giving a broad interpretation to the "technology" of our title. Starting at the beginning, Science, we have the review of basic nuclear physics data of Walker and Weaver for reactor kinetics, particularly, there fore, delayed neutron data. In the search for better and better accuracy, it is being realized that this involves the closest scrutiny of fundamental data, given to us here from the Birmingham school. Associated with this review of data is the review from Italy by Professor Pacilio and his co workers of the theory of reactor kinetics in the stochastic form, and a valuable compilation of the theory underlying a wide range of practical techniques. Tending more to technology come the papers by Jervis, reviewing the application of digital computers to the control of large nuclear power stations as developed in both the united Kingdom and Canada, Pickman's review of the design of fuels for heavy water reactors, and the account by Ishi kawa and Inabe of the new Japanese Research Reactor Program, itself initially directed largely to fuel element studies. The balance of the volume is made up of more philoso phical contributions to the practicalities of nuclear power.
More details
Edition
Softcover reprint of the original 1st ed. 1979
Language
English
Place of publication
New York
United States
Target group
Professional and scholarly
Research
Illustrations
X, 565 p.
Dimensions
Height: 235 mm
Width: 155 mm
Thickness: 31 mm
Weight
861 gr
ISBN-13
978-1-4613-2864-3 (9781461328643)
DOI
10.1007/978-1-4613-2862-9
Schweitzer Classification
Other editions
Additional editions
Ernest J. Henley
Advances in Nuclear Science and Technology
E-Book
12/2012
Springer
€53.49
Available for download
Ernest J. Henley
Advances in Nuclear Science and Technology
Book
01/1979
Kluwer Academic / Plenum Publishers
€96.00
Article not available at the moment
Content
Nuclear Physics Data for Reactor Kinetics.- I. Principles of Reactor Kinetics and Data Requirements.- II. Evaluated Nuclear Data Libraries.- III. Fission-Product Nuclear Data.- IV. Data on Delayed Neutrons.- V. Data on Heavy Elements.- Acknowledgments.- References.- The Analysis of Reactor Noise: Measuring Statistical Fluctuations in Nuclear Systems.- I. Introduction.- II. Theory.- III. Models for Interpreting Experiments.- IV. Epilogue.- Acknowledgments.- References.- On-Line Computers in Nuclear Power Plants - A Review.- Abstract.- I. Introduction.- II. Computer Functions and Application Classes.- III. Functions.- IV. Applications Classes.- V. Computer Hardware and Software.- VI. Examples of Systems in Operation.- VII. Ergonomic Factors and Operator Acceptance.- VIII. Reliability.- IX. Obsolescence and Designing for Replaceability.- X. Project Management.- XI. Program and Data Security.- XII. Licensing of Initial Design and Modification During Life.- XIII. Future Development.- XIV. Concluding Remarks.- Acknowledgments.- References.- Fuel for the SGHWR.- I. Introduction.- II. Fuel Design.- III. Operational Experience.- IV. Performance Models: The Seer-Sleuth Computer Code.- V. Behavior in Accident Conditions.- VI. Transient Modeling.- VII. Future Development.- References.- The Nuclear Safety Research Reactor (NSRR) in Japan.- I. Introduction.- II. NSRR Facility and Experimental Capability.- III. Experimental Research Program.- IV. Some Results of the Fuel Failure Experiments.- V. Future Plans.- References.- Practical Usage of Plutonium in Power Reactor Systems.- I. Popular Notions about Plutonium.- II. Historical Perspective and Review of Plutonium Properties.- III. Plutonium Recycle Alternatives.- IV. Current Status and Conclusions.- References.- Computer AssistedLearning in Nuclear Engineering.- I. Introduction.- II. Educational Roles of the Digital Computer.- III. Claims for CAL.- IV. Computers in Nuclear Engineering Education.- V. The Role of Graphics in Computer-Assisted Learning.- VI. Current CAL Projects.- VII. A Typical CAL Program.- VIII. Transferring CAL Materials.- IX. Implementation.- X. Evaluation.- XI. Future Prospects for CAL in Nuclear Engineering.- XII. Summary and Conclusions.- References.- Nuclear Energy Centers.- I. Introduction.- II. Fuel Cycle and Facility Integration.- III. Modular Construction.- IV. Heat Rejection.- V. Conclusions.- References.