Data Formats and Procedures for the ENDF Neutron Cross Section Library Page: 1

                                
DATA FORMATS AND PROCEDURES
FOR THE ENDF NEUTRON CROSS SECTION LIBRARY
1. INTRODUCTION
2. GENERAL FEATURES OF THE EVALUATED NUCLEAR DATA FILE
3. RELATIONSHIP OF THE ENDF TO OTHER DATA SYSTEMS
3.1 Experimental Data Libraries
3.2 Processing Codes and Neutronics Calculations
4. GENERAL DESCRIPTION OF THE ENDF LIBRARY
4.1 Definitions and Conventions
4.2 Structure of an ENDF Data Tape
4.3 Representation of Data
5. GENERAL DESCRIPTION OF THE DATA FORMATS
5.1 Nomenclature
5.2 Types of Binary Records
5.3 Card Image (BCD) Format

FILE 1, GENERAL INFORMATION
6.1 Descriptive Data and Dictionary
6.1    Formats
6.1.2 Procedures
6.2 Number of Neutrons per Fission,
6.2.1 Formats
6.2.2 Procedures
6.3  Radioactive Decay Data (MT = 453
6.3.1 Formats
6.3.2 Procedures
6.4  Fission Product Yield Data (MT =
6.3.1 Formats
6.3.2 Procedures

(MT = 451)

v (MT = 452)

= 454)

6.

3)