Advances in Nuclear Science and Technology

Volume 14 Sensitivity and Uncertainty Analysis of Reactor Performance Parameters
1982. Auflage 1982
ISBN: 978-0-306-40994-3
Verlag: Springer Us

Buch, Englisch, 386 Seiten, Gewicht: 690 g

We have pleasure in presenting Volume Fourteen to our readers. Volume Fourteen signifies a new dimension for our series, a volume devoted to the development of a single timely topic, that of sensitivity to uncertainty. This is still a broad topic and has been treated as such by the se­ veral distinguished authors contributing to the volume from their extensive experience both in theory and practice. While the theme running through the volume emphasizes uncertainties in areas related to reactor physics, it is true to say that this field of application has much to offer other disciplines as well. Some of the authors are engaged in ex­ tensions to other areas. The volume may therefore appeal to a much wider audience who will appreciate a single and compre­ hensive overview of a methodology that is applicable to other fields. Notable developments in the field of nuclear engineering have included the formatting in recent versions of Evaluated Nuclear Data Files (e.g., ENDF/B and its variants) of cross­ section uncertainty, the general acceptance of good practice in the representation of error correlation matrices, and more recent developments in the application of Monte Carlo tech­ niques to sensitivity analysis in complex geometries.

Zielgruppe

Research

Autoren/Hrsg.

Lewins, Jeffery

Becker, Martin

Fachgebiete

• Naturwissenschaften Physik Quantenphysik Kernphysik

Inhaltsverzeichnis

A. Purpose.- B. Scope of this Work.- C. Background.- D. Organization and Content of the Presentation.- Uncertainty in the Nuclear Data Used for Reactor Calculations.- A. Relevant Aspects of a Cross Section Data Base.- B. The Description of Nuclear Data Uncertainties and Correlations.- C. The Evaluation of Nuclear Data Uncertainties.- D. Existing Nuclear Data Uncertainty Files.- E. Conclusions on Nuclear Data.- Calculational Methodology and Associated Uncertainties.- A. Cross Section Processing.- B. Calculational Methodology for the Design Problem.- C. Determination of Calculational Corrections and Associated Uncertainties for a Critical Assembly.- D. Concluding Remarks.- Integral Experiment Information for Fast Reactors.- A. Availability of Integral Experiment Information.- B. Relevance of Data for Reactor Design.- C. Accuracy of Integral Experiment Data.- D. Selection of Reliable Integral Data.- E. Need for Additional Integral Experiment Data.- F. Summary.- Sensitivity Functions for Uncertainty Analysis.- A. Introduction.- B. Theoretical Foundation.- C. Criticality Reset Sensitivities.- D. Group Sensitivities and Uncertainties.- E. Selection of Sensitivities Included in the Analysis.- F. Other Uses and Limitations of Sensitivity Functions.- G. Summary.- Combination of Differential and Integral Data.- A. Introduction.- B. Derivation of Least-Squares Adjustment.- C. Input Data to the Adjustment.- D. The Results of Adjustment.- E. Application to an LMFBR.- F. Summary.- New Developments in Sensitivity Theory.- A. Introduction.- B. Sensitivity Theory for Reactor Depletion and Safety Problems.- C. Constrained Sensitivity Theory.- D. Complex Performance Parameters.- E. Methods to Account for Spectral-Fine-Structure Effects.- F. High Order Sensitivity Analysis.- G. Summary.- Summary 363.