Brookhaven2009 ENDF 6 Formats Manual
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- Preface
- 0 INTRODUCTION
- 0.1 Introduction to the ENDF-6 Format
- 0.2 Philosophy of the ENDF System
- 0.3 General Description of the ENDF System
- 0.3.1 Library (NLIB, NVER, LREL, NFOR)
- 0.3.2 Incident Particles and Data Types (NSUB)
- 0.3.2.1 Incident-Neutron Data (NSUB=10)
- 0.3.2.2 Thermal Neutron Scattering (NSUB=12)
- 0.3.2.3 Fission Product Yield Data
- 0.3.2.4 Radioactive Decay Data (NSUB=4)
- 0.3.2.5 Charged-Particle (NSUB10010) and Photo-Nuclear (NSUB=0) Sub-libraries
- 0.3.2.6 Photo-Atomic Interaction Data (NSUB=3)
- 0.3.2.7 Electro-Atomic Interaction Data (NSUB=113)
- 0.3.2.8 Atomic Relaxation Data (NSUB=6)
- 0.4 Contents of an ENDF Evaluation
- 0.4.1 Material (MAT, MOD)
- 0.4.2 ENDF Data Blocks (Files - MF)
- 0.4.3 Reaction Nomenclature (MT)
- 0.4.3.1 Elastic Scattering
- 0.4.3.2 Simple Single Particle Reactions
- 0.4.3.3 Simple Multi-Particle Reactions
- 0.4.3.4 Breakup Reactions
- 0.4.3.5 Complex Reactions
- 0.4.3.6 Radiative Capture
- 0.4.3.7 Fission
- 0.4.3.8 Nonelastic Reaction for Photon Production
- 0.4.3.9 Special Production Cross Sections
- 0.4.3.10 Auxiliary MT Numbers
- 0.4.3.11 Sum Rules for ENDF
- 0.5 Representation of Data
- 0.6 General Description of Data Formats
- 0.7 ENDF Documentation
- 1 File 1: GENERAL INFORMATION
- 2 File 2: RESONANCE PARAMETERS
- 2.1 General Description
- 2.2 Resolved Resonance Parameters (LRU=1)
- 2.3 Unresolved Resonance Parameters (LRU=2)
- 2.4 Procedures for the Resolved and Unresolved Resonance Regions
- 2.4.1 Abbreviations
- 2.4.2 Interpolation in the Unresolved Resonance Region (URR)
- 2.4.3 Unresolved Resonances in the Resolved Resonance Range
- 2.4.4 Energy Range Boundary Problems
- 2.4.5 Numerical Integration Procedures in the URR
- 2.4.6 Doppler-broadening of File 3 Background Cross Sections
- 2.4.7 Assignment of Unknown J-Values
- 2.4.8 Competitive Width in the Resonance Region
- 2.4.9 Negative Cross Sections in the Resolved Resonance Region
- 2.4.10 Negative Cross Sections in the Unresolved Resonance Region
- 2.4.11 Use of Two Nuclear Radii
- 2.4.12 The Multilevel Adler-Gauss Formula for MLBW
- 2.4.13 Notes on the Adler-Adler Formalism
- 2.4.14 Multi-Level Versus Single-Level Formalisms in the Resolved and Unresolved Resonance Regions
- 2.4.15 Preferred Formalisms for Evaluating Data
- 2.4.16 Degrees of Freedom for Unresolved Resonance Parameters
- 2.4.17 Procedures for the Unresolved Resonance Region
- 2.4.18 Procedures for Computing Angular Distributions in the Resolved Resonance Range
- 2.4.19 Completeness and Convergence of Channel Sums
- 2.4.20 Channel Spin and Other Considerations
- 3 File 3: REACTION CROSS SECTIONS
- 4 File 4: ANGULAR DISTRIBUTIONS
- 5 File 5: ENERGY DISTRIBUTIONS
- 5.1 General Description
- 5.2 Formats
- 5.3 Procedures
- 5.4 Additional Procedures
- 5.4.1 General Comments
- 5.4.2 Tabulated Distributions (LF=1)
- 5.4.3 Maxwellian Spectrum (LF=7)
- 5.4.4 Evaporation Spectrum (LF=9)
- 5.4.5 Watt Spectrum (LF=11)
- 5.4.6 Madland-Nix Spectrum (LF=12)
- 5.4.7 Selection of the Integration Constant, U
- 5.4.8 Multiple Nuclear Temperatures
- 5.4.9 Average Energy for a Distribution
- 5.4.10 Additional Procedures for Energy-Dependent Fission Neutron Spectrum (Madland and Nix)
- 6 File 6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS
- 6.1 General Description
- 6.2 Formats
- 6.2.1 Unknown Distribution (LAW=0)
- 6.2.2 Continuum Energy-Angle Distributions (LAW=1)
- 6.2.3 Discrete Two-Body Scattering (LAW=2)
- 6.2.4 Isotropic Discrete Emission (LAW=3)
- 6.2.5 Discrete Two-Body Recoils (LAW=4)
- 6.2.6 Charged-Particle Elastic Scattering (LAW=5)
- 6.2.7 N-Body Phase-Space Distributions (LAW=6)
- 6.2.8 Laboratory Angle-Energy Law (LAW=7)
- 6.3 Procedures
- 7 File 7: THERMAL NEUTRON SCATTERING LAW DATA
- 8 File 8: DECAY AND FISSION PRODUCT YIELDS
- 9 File 9: MULTIPLICITIES OF RADIOACTIVE PRODUCTS
- 10 File 10: PRODUCTION CROSS SECTIONS FOR RADIONUCLIDES
- 11 File 11: GENERAL COMMENTS ON PHOTON PRODUCTION
- 12 File 12: PHOTON PRODUCTION YIELD DATA
- 13 File 13: PHOTON PRODUCTION CROSS SECTIONS
- 14 File 14: PHOTON ANGULAR DISTRIBUTIONS
- 15 File 15: CONTINUOUS PHOTON ENERGY SPECTRA
- 23 File 23: PHOTON INTERACTION
- 26 File 26: SECONDARY DISTRIBUTIONS FOR PHOTO- AND ELECTRO-ATOMIC DATA
- 27 File 27: ATOMIC FORM FACTORS OR SCATTERING FUNCTIONS
- 28 File 28: ATOMIC RELAXATION DATA
- 29 INTRODUCTION TO COVARIANCE FILES
- 30 File 30. COVARIANCES OF MODEL PARAMETERS
- 31 File 31. COVARIANCES OF FISSION
- 32 File 32. COVARIANCES OF RESONANCE PARAMETERS
- 33 File 33, COVARIANCES OF NEUTRON CROSS SECTIONS
- 34 File 34. COVARIANCES FOR ANGULAR DISTRIBUTIONS
- 35 File 35. COVARIANCES FOR ENERGY DISTRIBUTIONS
- 40 File 40. COVARIANCES FOR RADIONUCLIDE PRODUCTION
- Acknowledgments
- APPENDIX
- A Glossary
- B Definition of Reaction Types
- C ZA Designations of Materials and MAT Numbers
- D Resonance Region Formulae
- D.1 The Resolved Resonance Region (LRU=1)
- D.1.1 Single-Level Breit-Wigner (SLBW, LRF=1)
- D.1.2 Multilevel Breit-Wigner (MLBW, LRF=2)
- D.1.3 Reich-Moore (R-M, LRF=3)
- D.1.4 Adler-Adler (AA, LRF=4)
- D.1.5 General R-Matrix (GRM, LRF=5)
- D.1.6 Hybrid R-Function (HRF, LRF=6)
- D.1.7 R-Matrix Limited Format (RML, LRF=7)
- D.1.7.1 Energy-Differential (Angle-Integrated) Cross Sections (Non-Coulomb Channels)
- D.1.7.2 Angular Distributions
- D.1.7.3 Kinematics for Angular Distributions of Elastic Scattering
- D.1.7.4 Spin and Angular Momentum Conventions
- D.1.7.5 Extensions to R-Matrix Theory
- D.1.7.6 Modifications for Charged Particles
- D.2 The Unresolved Resonance Region (LRU=2)
- D.3 The Competitive Width
- D.1 The Resolved Resonance Region (LRU=1)
- E Kinematic Formulas
- F Summary of Important ENDF Rules
- G Maximum Dimensions of ENDF Parameters
- H Recommended Values of Physical Constants
- I Historic perspective by Norman E. Holden