ENDF-6 Formats Manual - Brookhaven National Laboratory
CSEWG Document ENDF-102BNL-90365-2009Report BNL-XXXXX-2009ENDF-6 Formats ManualData Formats and Procedures for the Evaluated Nuclear Data FileENDF/B-VI and ENDF/B-VIIWritten by the Members of the Cross Sections Evaluation Working GroupLast Revision Edited byM. Herman and A. TrkovJune 2009National Nuclear Data CenterBrookhaven National LaboratoryUpton, NY 11973-5000www.nndc.bnl.govNotice: This manuscript has been authored by employees of Brookhaven Science Associates, LLC under Contract No. DEAC02-98CH10886 with the U.S. Department of Energy. The publisher by accepting the manuscript for publication acknowledgesthat the United States Government retains a non-exclusive, paid-up, irrevocable, world-wide license to publish or reproducethe published form of this manuscript, or allow others to do so, for United States Government purposes.
DISCLAIMERThis report was prepared as an account of work sponsored by an agency of the UnitedStates Government. Neither the United States Government nor any agency thereof, nor anyof their employees, nor any of their contractors, subcontractors, or their employees, makesany warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or any third party’s use or the results of such use of any information,apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or serviceby trade name, trademark, manufacturer, or otherwise, does not necessarily constitute orimply its endorsement, recommendation, or favoring by the United States Government orany agency thereof or its contractors or subcontractors. The views and opinions of authorsexpressed herein do not necessarily state or reflect those of the United States Governmentor any agency thereof.
PREFACEIn December 2006, the Cross Section Evaluation Working Group (CSEWG) of the UnitedStates released the new ENDF/B-VII.0 library. This represented considerable achievementas it was the 1st major release since 1990 when ENDF/B-VI has been made publiclyavailable. The two libraries have been released in the same format, ENDF-6, which hasbeen originally developed for the ENDF/B-VI library. In the early stage of work on theVII-th generation of the library CSEWG made important decision to use the same formats.This decision was adopted even though it was argued that it would be timely to modernizethe formats and several interesting ideas were proposed. After careful deliberation CSEWGconcluded that actual implementation would require considerable resources needed tomodify processing codes and to guarantee high quality of the files processed by these codes.In view of this the idea of format modernization has been postponed and ENDF-6 formatwas adopted for the new ENDF/B-VII library.In several other areas related to ENDF we made our best to move beyond establishedtradition and achieve maximum modernization. Thus, the “Big Paper” on ENDF/B-VII.0has been published, also in December 2006, as the Special Issue of Nuclear Data Sheets107 (1996) 2931-3060. The new web retrieval and plotting system for ENDF-6 formatteddata, Sigma, was developed by the NNDC and released in 2007. Extensive paper has beenpublished on the advanced tool for nuclear reaction data evaluation, EMPIRE, in 2007.This effort was complemented with release of updated set of ENDF checking codes in 2009.As the final item on this list, major revision of ENDF-6 Formats Manual was made. Thiswork started in 2006 and came to fruition in 2009 as documented in the present report.I would like to thank Mike Herman, the ENDF library data manager at the NNDC, aswell as Andrej Trkov, IJS Ljubljana, for their dedicated effort on the revised manual. Theyconverted it into LaTeX, carefully checked and implemented updates since the latest 2005release and consolidated Manual into fully updated and revised version. Many thanks aredue to numerous CSEWG members and international colleagues for their useful commentsand observations on several draft versions. It should be stressed that even though theManual is maintained by the United States, active contribution from the international datacommunity is essential for achieving its high quality.It is my expectation that this major revision will be embraced by the data evaluators aswell as members of numerous user communities worldwide.Upton, June 2009Pavel ObložinskýCSEWG chair until January 2009
ContentsPrefaceI0 INTRODUCTION0.1 Introduction to the ENDF-6 Format . . . . . . . . . . . . . .0.2 Philosophy of the ENDF System . . . . . . . . . . . . . . . .0.2.1 Evaluated Data . . . . . . . . . . . . . . . . . . . . .0.2.2 ENDF/B Library . . . . . . . . . . . . . . . . . . . .0.2.3 Choices of Data . . . . . . . . . . . . . . . . . . . . .0.2.4 Experimental Data Libraries . . . . . . . . . . . . . .0.2.5 Processing Codes . . . . . . . . . . . . . . . . . . . . .0.2.6 Testing . . . . . . . . . . . . . . . . . . . . . . . . . .0.2.7 Documentation . . . . . . . . . . . . . . . . . . . . . .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 (NSUB 10010) andPhoto-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 . . . . . . . . . . . . . . .i.12223334444555999. . . . . . . . . . . . . . . . . . . . . . . . . . . .1010101111111212121315161819.
CONTENTS0.50.60.70.4.3.7 Fission . . . . . . . . . . . . . . . . . . . .0.4.3.8 Nonelastic Reaction for Photon Production0.4.3.9 Special Production Cross Sections . . . . .0.4.3.10 Auxiliary MT Numbers . . . . . . . . . . .0.4.3.11 Sum Rules for ENDF . . . . . . . . . . . .Representation of Data . . . . . . . . . . . . . . . . . . . .0.5.1 Definitions and Conventions . . . . . . . . . . . . . .0.5.1.1 Atomic Masses Versus Nuclear Masses . . .0.5.2 Interpolation Laws . . . . . . . . . . . . . . . . . . .0.5.2.1 One-dimensional Interpolation Schemes . .0.5.2.2 Two-Dimensional Interpolation Schemes . .General Description of Data Formats . . . . . . . . . . . . .0.6.1 Structure of an ENDF Data Tape . . . . . . . . . .0.6.2 Symbol Nomenclature . . . . . . . . . . . . . . . . .0.6.3 Types of Records . . . . . . . . . . . . . . . . . . . .0.6.3.1 TEXT Records . . . . . . . . . . . . . . . .0.6.3.2 CONT Records . . . . . . . . . . . . . . . .0.6.3.3 HEAD Records . . . . . . . . . . . . . . . .0.6.3.4 END Records . . . . . . . . . . . . . . . . .0.6.3.5 DIR Records . . . . . . . . . . . . . . . . .0.6.3.6 LIST Records . . . . . . . . . . . . . . . .0.6.3.7 TAB1 Records . . . . . . . . . . . . . . . .0.6.3.8 TAB2 Records . . . . . . . . . . . . . . . .0.6.3.9 INTG records . . . . . . . . . . . . . . . .ENDF Documentation . . . . . . . . . . . . . . . . . . . . .1 File 1: GENERAL INFORMATION1.1 Descriptive Data and Directory (MT 451) . . . . . . . .1.1.1 Formats . . . . . . . . . . . . . . . . . . . . . . . .1.1.2 Procedures . . . . . . . . . . . . . . . . . . . . . .1.2 Number of Neutrons per Fission, ν, (MT 452) . . . . . .1.2.1 Formats . . . . . . . . . . . . . . . . . . . . . . . .1.2.2 Procedures . . . . . . . . . . . . . . . . . . . . . .1.3 Delayed Neutron Data, ν d , (MT 455) . . . . . . . . . . .1.3.1 Formats . . . . . . . . . . . . . . . . . . . . . . . .1.3.2 Procedures . . . . . . . . . . . . . . . . . . . . . .1.4 Number of Prompt Neutrons per Fission, ν p , (MT 456) .1.4.1 Formats . . . . . . . . . . . . . . . . . . . . . . . .1.4.2 Procedures . . . . . . . . . . . . . . . . . . . . . .1.5 Components of Energy Release Due to Fission (MT 458)1.5.1 Formats . . . . . . . . . . . . . . . . . . . . . . . .1.5.2 Procedures . . . . . . . . . . . . . . . . . . . . . .1.6 Delayed Photon Data (MT 460) . . . . . . . . . . . . . .1.6.1 Formats . . . . . . . . . . . . . . . . . . . . . . . .1.6.1.1 Discrete Representation (LO 1) . . . . 3232.34343738393940414143434344444647484848
CONTENTS.494949492 File 2: RESONANCE PARAMETERS2.1 General Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .2.2 Resolved Resonance Parameters (LRU 1) . . . . . . . . . . . . . . . . . . .2.2.1 Formats . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .2.2.1.1 SLBW and MLBW (LRF 1 or 2) . . . . . . . . . . . . . .2.2.1.2 Reich-Moore (LRF 3) . . . . . . . . . . . . . . . . . . . .2.2.1.3 Adler-Adler (LRF 4) . . . . . . . . . . . . . . . . . . . . .2.2.1.4 General R-Matrix (LRF 5) . . . . . . . . . . . . . . . . . .2.2.1.5 Hybrid R-function (LRF 6) . . . . . . . . . . . . . . . . .2.2.1.6 R-Matrix Limited Format (LRF 7) . . . . . . . . . . . . .2.3 Unresolved Resonance Parameters (LRU 2) . . . . . . . . . . . . . . . . . .2.3.1 Formats . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .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 . . . . . . . . . . . . .2.4.8.1 Resolved Region . . . . . . . . . . . . . . . . . . . . . . . .2.4.8.2 Unresolved Region . . . . . . . . . . . . . . . . . . . . . . .2.4.9 Negative Cross Sections in the Resolved Resonance Region . . . . . .2.4.9.1 In the SLBW Formalism: . . . . . . . . . . . . . . . . . . .2.4.9.2 In the MLBW Formalism: . . . . . . . . . . . . . . . . . .2.4.9.3 In the R-matrix, Reich-Moore, and R-function Formalisms:2.4.9.4 In the Adler-Adler Formalism: . . . . . . . . . . . . . . . .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 . . . . . . . . . . . . . . . . . . . . . . .2.4.14.1 In the Resolved Resonance Region: . . . . . . . . . . . . .2.4.14.2 In the Unresolved Resonance Region: . . . . . . . . . . . .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 . . . . . . . . . . 7787878797980811.6.21.6.1.2 Continuous Representation (LO 2)Procedures . . . . . . . . . . . . . . . . . . .1.6.2.1 Discrete Representation (LO 1) .1.6.2.2 Continuous Representation (LO 2)iii.828283848486
CONTENTS2.4.18 Procedures for Computing Angular Distributions in the Resolved Resonance Range . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .2.4.18.1 Background . . . . . . . . . . . . . . . . . . . . . . . . . .2.4.18.2 Further Considerations . . . . . . . . . . . . . . . . . . . .2.4.18.3 Summary of Recommendations for Evaluation Procedures .2.4.19 Completeness and Convergence of Channel Sums . . . . . . . . . . .2.4.20 Channel Spin and Other Considerations . . . . . . . . . . . . . . . .3 File3.13.23.33: REACTION CROSS SECTIONSGeneral Description . . . . . . . . . . . . . . . . . . . . . . . . . .Formats . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .General Procedures . . . . . . . . . . . . . . . . . . . . . . . . . .3.3.1 Cross Sections, Energy Ranges, and Thresholds . . . . . . .3.3.2 Q-Values . . . . . . . . . . . . . . . . . . . . . . . . . . . .3.3.3 Relationship Between File 3 and File 2 . . . . . . . . . . . .3.4 Procedures for Incident Neutrons . . . . . . . . . . . . . . . . . . .3.4.1 Total Cross Section (MT 1) . . . . . . . . . . . . . . . . .3.4.2 Elastic Scattering Cross Section (MT 2) . . . . . . . . . .3.4.3 Nonelastic Cross Section (MT 3) . . . . . . . . . . . . . .3.4.4 Inelastic Scattering Cross Sections (MT 4,51-91) . . . . . .3.4.5 Fission (MT 18,19-21,38) . . . . . . . . . . . . . . . . . . .3.4.6 Charged-Particle Emission to Discrete and Continuum(MT 600-849) . . . . . . . . . . . . . . . . . . . . . . . . .3.5 Procedures for Incident Charged Particles and Photons . . . . . . .3.5.1 Total Cross Sections . . . . . . . . . . . . . . . . . . . . . .3.5.2 Elastic Scattering Cross Sections . . . . . . . . . . . . . . .3.5.3 Inelastic Scattering Cross Sections . . . . . . . . . . . . . .3.5.4 Stopping Power . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .Levels. . . . . . . . . . . . . . . . . . . . . . . . .4 File 4: ANGULAR DISTRIBUTIONS4.1 General Description . . . . . . . . . . . . . . . . . . . . . . . . . . . .4.2 Formats . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .4.2.1 Legendre Polynomial Coefficients (LTT 1, LI 0) . . . . . . . .4.2.2 Tabulated Probability Distributions (LTT 2, LI 0) . . . . . .4.2.3 Purely Isotropic Angular Distributions (LTT 0, LI 1) . . . . .4.2.4 Angular Distribution Over Two Energy Ranges (LTT 3, LI 0)4.3 Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .4.4 Procedures for Specific Reactions . . . . . . . . . . . . . . . . . . . . .4.4.1 Elastic Scattering (MT 2) . . . . . . . . . . . . . . . . . . . .4.4.2 Discrete Channel Two-Body Reactions . . . . . . . . . . . . . .4.4.3 Other Particle-Producing Reactions . . . . . . . . . . . . . . 100100101102102104105105105106106107107108109
CONTENTS5 File 5: ENERGY DISTRIBUTIONS5.1 General Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .5.1.1 Secondary Energy Distribution Laws . . . . . . . . . . . . . . . . . .5.1.1.1 Arbitrary Tabulated Function (LF 1) . . . . . . . . . . . .5.1.1.2 General Evaporation Spectrum (LF 5) . . . . . . . . . . . .5.1.1.3 Simple Maxwellian Fission Spectrum (LF 7) . . . . . . . .5.1.1.4 Evaporation Spectrum (LF 9) . . . . . . . . . . . . . . . .5.1.1.5 Energy-Dependent Watt Spectrum (LF 11) . . . . . . . . .5.1.1.6 Energy-Dependent Fission Neutron Spectrum (Madland andNix) (LF 12) . . . . . . . . . . . . . . . . . . . . . . . . . .5.2 Formats . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .5.2.1 Arbitrary Tabulated Function (LF 1) . . . . . . . . . . . . . . . . .5.2.2 General Evaporation Spectrum (LF 5) . . . . . . . . . . . . . . . .5.2.3 Simple Maxwellian Fission Spectrum (LF 7) . . . . . . . . . . . . .5.2.4 Evaporation Spectrum (LF 9) . . . . . . . . . . . . . . . . . . . . .5.2.5 Energy-Dependent Watt Spectrum (LF 11) . . . . . . . . . . . . . .5.2.6 Energy-Dependent Fission Neutron Spectrum(Madland and Nix) (LF 12) . . . . . . . . . . . . . . . . . . . . . .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-DependentFission Neutron Spectrum (Madland and Nix) . . . . . . . . . . . .5.4.10.1 Region I (a EF , b EF ) . . . . . . . . . . . . . . . . . . .5.4.10.2 Region II (a EF , b EF ) . . . . . . . . . . . . . . . . . .5.4.10.3 Region III (a EF , b EF ) . . . . . . . . . . . . . . . . . .1101101111121121121121136 File 6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS6.1 General Description . . . . . . . . . . . . . . . . . . . . . . . . . . . .6.2 Formats . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .6.2.1 Unknown Distribution (LAW 0) . . . . . . . . . . . . . . . . .6.2.2 Continuum Energy-Angle Distributions (LAW 1) . . . . . . .6.2.2.1 Legendre Coefficients Representation (LANG 1) . . .6.2.2.2 Kalbach-Mann Systematics Representation (LANG 2)6.2.2.3 Tabulated Function Representation (LANG 11-15) . .6.2.3 Discrete Two-Body Scattering (LAW 2) . . . . . . . . . . . .6.2.4 Isotropic Discrete Emission (LAW 3) . . . . . . . . . . . . . 22
CONTENTS6.36.2.5 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) . .Procedures . . . . . . . . . . . . . . . . . . . . . . .6.3.1 Elastic Scattering . . . . . . . . . . . . . . .6.3.2 Photons . . . . . . . . . . . . . . . . . . . . .6.3.3 Particles . . . . . . . . . . . . . . . . . . . .6.3.4 Neutron Emission . . . . . . . . . . . . . . .6.3.5 Recoil Distributions . . . . . . . . . . . . . .6.3.6 Elements as Targets . . . . . . . . . . . . . .6.3.7 CM versus LAB Coordinate System . . . . .6.3.8 Phase Space . . . . . . . . . . . . . . . . . .7 File 7: THERMAL NEUTRON SCATTERING LAW DATA7.1 General Description . . . . . . . . . . . . . . . . . . . . . . . .7.2 Coherent Elastic Scattering . . . . . . . . . . . . . . . . . . . .7.2.1 Formats for Coherent Elastic Scattering . . . . . . . . .7.2.2 Procedures for Coherent Elastic Scattering . . . . . . . .7.3 Incoherent Elastic Scattering . . . . . . . . . . . . . . . . . . .7.3.1 Format for Incoherent Elastic Scattering . . . . . . . . .7.3.2 Procedures for Incoherent Elastic Scattering . . . . . . .7.4 Incoherent Inelastic Scattering . . . . . . . . . . . . . . . . . .7.4.1 Formats for Incoherent Inelastic Scattering . . . . . . .7.4.2 Procedures for Incoherent Inelastic Scattering . . . . . .8 File 8: DECAY AND FISSION PRODUCT8.1 General Description . . . . . . . . . . . . .8.2 Radioactive Nuclide Production . . . . . . .8.2.1 Formats . . . . . . . . . . . . . . . .8.2.2 Procedures . . . . . . . . . . . . . .8.3 Fission Product Yield Data(MT 454, MT 459) . . . . . . . . . . . . .8.3.1 Formats . . . . . . . . . . . . . . . .8.3.2 Procedures . . . . . . . . . . . . . .8.4 Radioactive Decay Data (MT 457) . . . .8.4.1 Formats . . . . . . . . . . . . . . . .8.4.2 Procedures . . . . . . . . . . . . . .9 File9.19.29.39: MULTIPLICITIESGeneral Description . .Formats . . . . . . . . .Procedures . . . . . . 145146146146147147150151YIELDS. . . . . . . . . . . . . . . . . . . . .153153153155156.157158158159163164OF RADIOACTIVE PRODUCTS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .168168168169vi.
CONTENTS10 File10.110.210.310: PRODUCTION CROSSGeneral Description . . . . . .Formats . . . . . . . . . . . . .Procedures . . . . . . . . . . .SECTIONS. . . . . . . . . . . . . . . . . . . . . .FOR RADIONUCLIDES. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .17117117117211 File 11: GENERAL COMMENTS ON PHOTON PRODUCTION17411.1 General Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17412 File 12: PHOTON PRODUCTION YIELD DATA12.1 General Description . . . . . . . . . . . . . . . . . . . .12.2 Formats . . . . . . . . . . . . . . . . . . . . . . . . . . .12.2.1 Option 1: Multiplicities (LO 1) . . . . . . . . .12.2.2 Option 2: Transition Probability Arrays (LO 2)12.3 Procedures . . . . . . . . . . . . . . . . . . . . . . . . .13 File13.113.213.313.413: PHOTON PRODUCTION CROSSGeneral Description . . . . . . . . . . . . .Formats . . . . . . . . . . . . . . . . . . . .Procedures . . . . . . . . . . . . . . . . . .Preferred Representations . . . . . . . . . .178178178179181182SECTIONS. . . . . . . . . . . . . . . . . . . . . . . . . . . . .18418418418618714 File 14: PHOTON ANGULAR DISTRIBUTIONS14.1 General Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .14.2 Formats . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .14.2.1 Isotropic Distribution (LI 1) . . . . . . . . . . . . . . . . . . . . . .14.2.2 Anisotropic Distribution with Legendre Coefficient Representation(LI 0, LTT 1) . . . . . . . . . . . . . . . . . . . . . . . . . . . . .14.2.3 Anisotropic Distribution with Tabulated Angular Distributions (LI 0,LTT 2) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .14.3 Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .18818818919015 File15.115.215.315: CONTINUOUS PHOTON ENERGY SPECTRAGeneral Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .Formats . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .19319319419523 File23.123.223.323.423: PHOTON INTERACTIONGeneral Comments on Photon ProductionGeneral Description . . . . . . . . . . . .Formats . . . . . . . . . . . . . . . . . . .Procedures . . . . . . . . . . . . . . . . .196196196197197.19019119126 File 26:SECONDARY DISTRIBUTIONS FOR PHOTO- ANDELECTRO-ATOMIC DATA19826.1 General Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19826.2 Formats . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 199vii
CONTENTS26.2.1 Continuum Distribution (LAW 1) . . . . . . . . . . . . . . . . . . . 20026.2.2 Two-Body Angular Distribution (LAW 2) . . . . . . . . . . . . . . 20026.2.3 Energy Transfer for Excitation (LAW 8) . . . . . . . . . . . . . . . 20027 File 27: ATOMIC FORM FACTORS27.1 General Description . . . . . . . . . .27.1.1 Incoherent Scattering . . . .27.1.2 Cooherent Scattering . . . .27.2 Formats . . . . . . . . . . . . . . . .27.3 Procedures . . . . . . . . . . . . . .28 File28.128.228.328: ATOMIC RELAXATIONGeneral Description . . . . . . .Formats . . . . . . . . . . . . . .Procedures . . . . . . . . . . . .OR SCATTERING FUNCTIONS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .201201201202202203DATA204. . . . . . . . . . . . . . . . . . . . . . . . 204. . . . . . . . . . . . . . . . . . . . . . . . 205. . . . . . . . . . . . . . . . . . . . . . . . 20629 INTRODUCTION TO COVARIANCE FILES21029.1 General Comments . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21030 File 30. COVARIANCES OF MODEL PARAMETERS30.1 General Comments . . . . . . . . . . . . . . . . . . . . . .30.1.1 Definitions . . . . . . . . . . . . . . . . . . . . . .30.1.2 Treatment of Various Data Types . . . . . . . . .30.1.3 Multigrouped Sensitivities . . . . . . . . . . . . . .30.2 Formats . . . . . . . . . . . . . . . . . . . . . . . . . . . .30.2.1 Directory and Correspondence Table (MT 1) . . .30.2.2 Covariance Matrix (MT 2) . . . . . . . . . . . . .30.2.3 Sensitivities (MT 11-999) . . . . . . . . . . . . . .30.3 Additional Procedures . . . . . . . . . . . . . . . . . . . .30.3.1 Relation of MP-values to Physical Parameters . . .30.3.2 Parameter Values . . . . . . . . . . . . . . . . . .30.3.3 Eigenvalue Representation . . . . . . . . . . . . . .30.3.4 Thinning of Sensitivity Information . . . . . . . .30.3.5 Cross-file Correlations . . . . . . . . . . . . . . . .30.4 Multigroup Applications of Parameter Covariances . . . .31 File31.131.231.331. COVARIANCES OFGeneral Comments . . . . .Formats . . . . . . . . . . .Procedures . . . . . . . . ISSION ν225. . . . . . . . . . . . . . . . . . . . . . . . . . . 225. . . . . . . . . . . . . . . . . . . . . . . . . . . 225. . . . . . . . . . . . . . . . . . . . . . . . . . . 22632 File 32. COVARIANCES OF RESONANCE PARAMETERS32.1 General Comments . . . . . . . . . . . . . . . . . . . . . . . . . .32.2 Formats . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .32.2.1 Compatible Resolved Resonance Format (LCOMP 0) . .32.2.2 General Resolved Resonance Formats (LCOMP 1) . . . .viii.228228230231232
BW and MLBW (LRF 1 or 2) . . . . . . . . . . . . . .Reich-Moore (LRF 3) . . . . . . . . . . . . . . . . . . . .Adler-Adler (LRF 4) . . . . . . . . . . . . . . . . . . . . .R-Matrix Limited Format (LRF 7) . . . . . . . . . . . . .Format for Long-Range Covariance Subsubsections(LRU 1) . . . . . . . . . . . . . . . . . . . . . . . . . . . .32.2.3 Resolved Resonance Compact Covariance Format (LCOMP 2) . . .32.2.3.1 SLBW and MLBW (LRF 1 or 2) . . . . . . . . . . . . . .32.2.3.2 Reich-Moore (LRF 3) . . . . . . . . . . . . . . . . . . . .32.2.3.3 R-Matrix Limited Format (LRF 7) . . . . . . . . . . . . .32.2.4 Unresolved Resonance Format (LRU 2) . . . . . . . . . . . . . . . .32.3 Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .33 File 33, COVARIANCES OF NEUTRON CROSS SECTIONS33.1 General Comments . . . . . . . . . . . . . . . . . . . . . . . . . .33.2 Formats . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .33.2.1 Subsections . . . . . . . . . . . . . . . . . . . . . . . . . .33.2.2 Sub-Subsections . . . . . . . . . . . . . . . . . . . . . . .33.2.2.1 NC-type Sub-Subsections . . . . . . . . . . . . .33.2.2.2 NI-type Sub-Subsections . . . . . . . . . . . . . .33.2.3 Lumped Reaction Covariances . . . . . . . . . . . . . . .33.3 Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .33.3.1 Ordering of Sections, Subsections and Sub-Subsections . .33.3.2 Completeness . . . . . . . . . . . . . . . . . . . . . . . . .33.3.3 Other Procedures . . . . . . . . . . . . . . . . . . . . . .33.3.4 Examples . . . . . . . . . . . . . . . . . . . . . . . . . . .33.3.4.1 Use of LTY 1 and LTY 2 NC-type Subsections33.3.4.2 Use of LTY 0, NC-type Sub-Subsections . . . 5225726326326326526626926927234 File34.134.234.334. COVARIANCES FORGeneral Comments . . . . . .Formats . . . . . . . . . . . .Procedures . . . . . . . . . .ANGULAR. . . . . . . . . . . . . . . . . . . . . .35 File35.135.235.335. COVARIANCES FORGeneral Comments . . . . . .Formats . . . . . . . . . . . .Procedures . . . . . . . . . .ENERGY DISTRIBUTIONS280. . . . . . . . . . . . . . . . . . . . . . . . . . 280. . . . . . . . . . . . . . . . . . . . . . . . . . 280. . . . . . . . . . . . . . . . . . . . . . . . . . 28240 File40.140.240.340.440.540. COVARIANCES FOR RADIONUCLIDE PRODUCTIONGeneral Comments . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
National Nuclear Data Center Brookhaven National Laboratory Upton, NY 11973-5000 www.nndc.bnl.gov Notice: This manuscript has been authored by employees of Brookhaven Science Associates, LLC under Contract No. DE-AC02-98CH10886 with the U.S. Department of Energy. The publisher by accepting the manuscript for publication acknowledges
Preparing for ENDF/B-VIII David Brown, Cross Section Evaluation Working Group (CSEWG) Submitted to National Nuclear Data Center Library Held at Brookhaven Lab, Upton NY November 6-12, 2016 March 7, 2017 National Nuclear Data Center Brookhaven National Laboratory U.S. Department of Energy Office of Science, Office of Nuclear Physics
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