Nuclear Fission and Neutron-Induced Fission Cross-Sections

Nuclear Fission and Neutron-Induced Fission Cross-Sections

A Nuclear Energy Agency Nuclear Data Committee (OECD) Series: Neutron Physics and Nuclear Data in Science and Technology

1st Edition - January 1, 1981

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  • Authors: G. D. James, J. E. Lynn, A. Michaudon
  • eBook ISBN: 9781483189765

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Nuclear Fission and Neutron-Induced Fission Cross-Sections is the first volume in a series on Neutron Physics and Nuclear Data in Science and Technology. This volume serves the purpose of providing a thorough description of the many facets of neutron physics in different fields of nuclear applications. This book also attempts to bridge the communication gap between experts involved in the experimental and theoretical studies of nuclear properties and those involved in the technological applications of nuclear data. This publication will be invaluable to those interested in studying nuclear fission and neutron-induced fission cross-sections, as well as other relevant concepts.

Table of Contents

  • List of Abbreviations

    Chapter I Introduction

    Chapter II Basic Physics of the Fission Process

    II.A Introduction

    II.B Various Phases of the Fission Process

    II.B.1 Formation of the Initial State

    II.B.2 From the Initial State to Scission

    II.B.3 From Scission to the Formation of Fission Products (Fast Processes)

    II.B.4 Deexcitation of the Fission Products (Delayed Processes)

    II.C Some Properties of the Low-energy Fission of Actinide Nuclei

    II.C.1 Mass Distribution of the Fission Products

    II.C.2 Prompt-Fission Neutron Emission

    II.C.3 Kinetic Energy of the Fission Fragments

    II.C.4 Energy Balance in Fission

    II.D Neutron-induced Fission

    II.D.1 Introduction

    II.D.2 Fissile and Non-Fissile Nuclei

    II.D.3 Fast-Neutron Fission Cross-Sections

    II.D.4 Fission Cross-Sections in the Resonance Region

    II.D.5 Thermal-Neutron Fission Cross-Sections

    II.D.6 A. Bohr's Theory of Fission Exit Channels

    II.D.7 Some Effects Associated with a Double-Hump Shape of the Fission Barrier

    Chapter III Fission Cross-section Requirements for the Nuclear Energy Program

    III.A Introduction

    III.B Fuel Cycles and the Qualitative Role of Nuclear Data

    III.B.1 Fuel Cycles and Important Fission Cross-Sections

    III.B.2 Importance of the Energy Dependence of Cross-Sections

    III.C Reactor Calculations and the Quantitative Role of Nuclear Data

    III.C.1 Group Averaged Cross-Sections

    III.C.2 Reactor Calculations for which Nuclear Data are Required

    III.C.3 Sensitivity of Calculations to Nuclear Data Uncertainties

    III.C.4 Examples of Sensitivity Calculations

    III.D Integral Measurements

    III.D.1 Methods for Taking into Account the Results of Integral Measurements

    III.D.2 The Accuracy Requirements for Cross-Section Measurements When Integral Measurements are Taken into Account

    III.D.3 Examples of the Changes in Cross-Section Measurement Requirements when Integral Measurements are Taken into Account

    III.E Summary of Fission Cross-section Requirements for the Nuclear Energy Program

    III.E.1 Primary Actinides

    III.E.2 Secondary Actinides

    Chapter IV Measurements of Fission Cross-sections

    IV.A Introduction

    IV.B Essentials of Cross-section Measurements

    IV.C Measurement Techniques

    IV.D Fission Detection

    IV.D.1 Fission Fragment Detection

    IV.D.2 Fission-Neutron and Fission-Gamma-Ray Detection

    IV.E Selected Examples of Fission Cross-section Measurements

    IV.E.1 Precise Measurement of the 2200 m/s Fission Cross-Section of 235U

    IV.E.2 High Resolution Fission Cross-Section Measurements in the Resonance Region for the Main Fissile Isotopes

    IV.E.3 Measurement of the 235U Fission Cross-Section from 1 to 6 MeV

    IV.E.4 Measurement of the 235U Fission Cross-Section in the Energy Range 1 keV to 1 MeV

    IV.E.5 Measurement of the 235 U Fission Cross-Section in the Fast-Neutron Energy Range (35 keV to 3.5 MeV)

    IV.E.6 Measurement of the 238U to 235U Fission Cross-Section Ratio Over the Energy Range 1 keV to 30 MeV

    IV.E.7 Fission Cross-Section Measurement for a Short-Lived Isotope

    IV.F Data Reduction and Storage

    IV.F.1 Data Reduction

    IV.F.2 Data Storage

    IV.G Data Analysis

    IV.G.1 Introduction

    IV.G.2 Resonance Formalisms

    IV.G.3 Doppler and Resolution Broadenings

    IV.G.4 Resonance Analysis

    IV.G.5 Resolved and Unresolved Resonance Regions

    IV.H Data Evaluation

    IV.H.1 Introduction

    IV.H.2 Need for Evaluated Cross-Sections

    IV.H.3 Uncertainties in Measured and Evaluated Fission Cross-Sections

    IV.H.4 Cross-Sections of Fissile Nuclei Below 1 eV

    IV.H.5 The 235U Fission Cross-Section from 1 eV to 100 keV

    IV.H.6 The 235U Fission Cross-Section from 0.1 to 20 MeV

    IV.H.7 Conclusions

    IV.I Comparison of Experimental Results with Needs

    IV.I.1 Fissile Isotopes; 233U, 235U, 239Pu, and 241Pu

    IV.I.2 Fertile Isotopes: 232Th, 238U, and 240Pu

    IV.I.3 Secondary Actinides

    IV.J Future Measurements

    Chapter V Theoretical Methods for Calculating the Cross-sections of Fissionable Nuclei

    V.A Introduction

    V.B The Compound Nucleus and Hauser-feshbach Theory

    V.B.1 The Compound Nucleus^ Independence of Formation and Decay

    V.B.2 The Compound Nucleus Formation Cross-Section: Relation to the Transmission Coefficient

    V.B.3 Formulations and Models for the Transmission Coefficient

    V.C Calculation of Neutron Transmission Coefficients

    V.C.1 Statistical Concepts for High Neutron Energies

    V.C.2 Nuclear Structure Effects in Neutron Transmission Coefficients

    V.D Radiative Transmission Coefficients

    V.D.1. Statistical Concepts

    V.D.2 Nuclear Structure Effects

    V.E Level Densities

    V.E.1 Independent Quasi-Particle States

    V.E.2 The Blocking Effect; The Independent Particle Model

    V.E.3 Rotational States

    V.E.4 Experimental Data on Level Densities

    V.F Fission Transmission Coefficients

    V.F.1 Statistical Concepts

    V.F.2 Structure Effects in Fission Transmission Coefficients

    V.F.3 Assessment of Barrier Parameters

    V.G Computational Methods for Calculating Cross-sections of Fissionable Nuclides

    V.G.l Introduction

    V.G.2 The Program EVAPF

    V.G.3 The Program AVXS

    V.G.4 Examples of Calculated Cross-Sections

    V.H Conclusions

    Chapter VI Conclusion



    Subject Index

Product details

  • No. of pages: 294
  • Language: English
  • Copyright: © Pergamon 1981
  • Published: January 1, 1981
  • Imprint: Pergamon
  • eBook ISBN: 9781483189765

About the Authors

G. D. James

J. E. Lynn

A. Michaudon

About the Editors

A. Michaudon

S. W. Cierjacks

R. E. Chrien

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