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The following is based on ENDF-102, Data Formats and Procedures for the Evaluated Nuclear Data File ENDF-6. Reaction cross sections and auxiliary quantities are given in File 3 as functions of energy E, where E is the incident energy in the laboratory system. They are given as energy-cross section (or auxiliary data) pairs. An interpolation scheme is given that specifies the energy variation of the data for incident energies between a given energy point and the next higher point. File 3 is divided into sections, each containing the data for a particular reaction (MT number). The sections are ordered by increasing MT number. As usual, each section starts with a HEAD record and ends with a SEND record. The file ends with a FEND record. Formats The following quantities are defined:
The structure of a section is
[MAT, 3, MT/ ZA, AWR, 0, 0, 0, 0] HEAD
[MAT, 3, MT/ QM, QI, 0, LR, NR, NP/ EINT/ S(E)] TAB1
[MAT, 3, 0/ 0.0, 0.0, 0, 0, 0, 0] SEND
This standardized shorthand notation is used throughout the
ENDF format manual to show what parameters appear in the
various fields.
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| 23 January 1998 | T-2 Nuclear Information Service | ryxm@lanl.gov |