1. NAME AND TITLE
ADENA: Code System for Application of Adjusted Data in Calculating Fission-Product
Decay Energies and Spectra.
Los Alamos National Laboratory, Los Alamos, New Mexico.
3. CODING LANGUAGE AND COMPUTER
Fortran V (P00190C000000) or Fortran IV (P00190I303300); CDC 7600 (P00190C000000) or
IBM 3033 (P00190I303300).
4. NATURE OF PROBLEM SOLVED
ADENA calculates fission-product beta- and gamma-ray decay energies and spectra in 19 or fewer
energy groups from a mixture of 235U and 239Pu fuels at user specified cooling times. It can be used for
a wide variety of reactor operational and safety related computations where aggregate fission-product
decay spectra are needed. A correction for neutron absorption in the fission products is included.
5. METHOD OF SOLUTION
ADENA uses aggregate, adjusted data derived from a combination of several experiments and
summation results based on the ENDF/B-V fission-product file. The calculation method is
approximate and comparisons are made to experimental measurements, to the ANSI/ANS 5.1-1979
standard, and to other calculational methods.
6. RESTRICTIONS OR LIMITATIONS
ADENA allows a maximum of 50 times steps per run. The energy bounds must be a subset of the
19-group structure specified in the ADENA report (LA-9362-MS). The plotting option has been
dummied out in the IBM version.
7. TYPICAL RUNNING TIME
ADENA requires less than 30 sec. of CPU time per time step on the CDC 7600 computer. The
sample problem, version (I3033), used .812 cpu seconds on the IBM 3033 computer.
8. COMPUTER HARDWARE REQUIREMENTS
Version (C0000) was designed for the CDC computer. Version (I3033) was modified by RSIC and
is operable on the IBM 3033 computer.
9. COMPUTER SOFTWARE REQUIREMENTS
A Fortran V (C0000) or Fortran IV (I3033) compiler is required. The DISSPLA graphics library
is necessary for the plotting option.
a. Included in the documentation:
D. C. George, R. J. LaBauve, and T. R. England, "Application of Adjusted Data in Calculating
Fission-Product Decay Energies and Spectra," LA-9362-MS (June 1982).
b. Background information:
D. C. George, R. J. LaBauve, T. R. England, "Calculating Fission-Product Decay Energies and
Spectra using Adjusted Data," LA-UR 82-94 (June 1982).
11. CONTENTS OF CODE PACKAGE
Included are the referenced document and one (1.2MB) DOS diskette which contains the source
code and sample problem input and output.
12. DATE OF ABSTRACT
February 1983; revised October 1983, April 1984, August 1984.
KEYWORDS: ENDF FORMAT; ENDF/B-V; FISSION PRODUCTS; PARAMETRIC MODELS; RADIATION SOURCE GENERATOR