last modified: 23-FEB-1988 | catalog | categories | new | search |

IAEA1330 HEATER.

HEATER, Reaction Rate Tables from Cross-Sections with Weighting

top ]
1. NAME OR DESIGNATION OF PROGRAM:  HEATER.
top ]
2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
HEATER-87.1 IAEA1330/01 Tested 23-FEB-1988

Machines used:

Package ID Orig. computer Test computer
IAEA1330/01 IBM 3033 DEC VAX 11/780
top ]
3. DESCRIPTION OF PROGRAM OR FUNCTION

HEATER is designed to calculate a linearly interpolate table of spectrum averaged reaction rates starting from tabulated linear interpolable energy dependent cross sections and a weighting spectrum which is either: (1) V*Maxwellian; (2) a general linearly interpolable tabulated weighting spectrum.
top ]
4. METHOD OF SOLUTION

HEATER uses the interval halving algorithm which is described in detail in the documentation for program LINTAB.
top ]
5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
top ]
6. TYPICAL RUNNING TIME:
top ]
7. UNUSUAL FEATURES OF THE PROGRAM:
top ]
8. RELATED AND AUXILIARY PROGRAMS

The following programs are all part of the PRE-PRO94 package.

COMPLOT:  Compares ENDF/B formatted data from two separate input

          files. Results are in graphical form.

CONVERT:  Automatically converts a FORTRAN program for use on any

          one of a variety of: (1) computers; (2) compilers;

          (3) precisions; (4) installations; (5) standard or

          non-standard file names.

DICTION:  Creates a reaction index for each material.

EVALPLOT: Plots  data in  the ENDF/B format.

FIXUP:    Reads  evaluated  data  in  the ENDF/B  format;

          performs corrections and outputs the results in the

          ENDF/B format.

GROUPIE   calculates unshielded group averaged cross sections,

          Bondarenko self-shielded group averaged cross sections,

          and multiband parameters from data in the ENDF/B format.

LEGEND:   Calculates linearly interpolable tabulated angular

          distributions starting from data in the ENDF/B format.

LINEAR:   Converts cross sections in the ENDF/B format (File 3, 23,
          and 27) to linearly interpolable form (in energy and

          cross section) and outputs the result in the ENDF/B

          format.

MERGER:   Selectively retrieves data by MAT/MF/MT or ZA/MF/MT from

          up to 10 ENDF/B data tapes and merges the data into a

          single MAT/MF/MT ordered output file.

MIXER:    Calculates the energy dependent cross sections for a

          composite mixture.

PLOTTAB:  Plots any combination of continuous curves and/or points

          (with associated error bars) using user-supplied titles

          and (x,y) axis labels and units.

RECENT:   Reconstructs energy-dependent cross sections from a

          combination of resonance parameters and tabulated

          background cross sections in the ENDF/B format.

RELABEL:  relabels a ENDF/B preprocessing program so that statement
          labels are in increasing order in increments of 10 within
          each routine.

SIGMA-1:  Doppler broadens evaluated cross sections in the linear-

          linear interpolation form of the ENDF/B format.

SIXPAK:   Checks all double-differential ENDF/B-VI format data

          (MF=6) and outputs equivalent uncorrelated data (MF=4, 5,
          12, 14, and 15)

VIRGIN:   Calculates uncollided flux and reactions due to

          transmission of a monodirectional beam of neutrons

          through any thickness of material.
top ]
9. STATUS
Package ID Status date Status
IAEA1330/01 23-FEB-1988 Tested at NEADB
top ]
10. REFERENCES:
IAEA1330/01, included references:
- D.E. Cullen and J.J. Smith:
  LINTAB and HEATER Program Package: Computer Codes
  for Model Parameters and Cross-Section Data (Version 87-1).
  IAEA-NDS-84, Rev. 0  (July 1987)
- D.E. Cullen, J.J. Smith and P.K. McLaughlin:
  Implementing and Testing the LINTAB, HEATER
  and PLOTTAB Code Package
  IAEA-NDS-85, Rev. 1  (September 1987)
top ]
11. MACHINE REQUIREMENTS:
top ]
12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA1330/01 FORTRAN-77
top ]
13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
top ]
14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
top ]
15. NAME AND ESTABLISHMENT OF AUTHORS

              IAEA Nuclear Data Section
              P.O. Box 100
              A-1400 VIENNA, Austria
top ]
16. MATERIAL AVAILABLE
IAEA1330/01
File name File description Records
IAEA1330_01.001 HEATER Information file 85
IAEA1330_01.002 HEATER Fortran source file 1556
IAEA1330_01.003 HEATER Command file 8
IAEA1330_01.004 HEATER Input file 18
IAEA1330_01.005 HEATER Maxwellian weighting spectrum 1042
IAEA1330_01.006 HEATER Output file 1924
IAEA1330_01.007 HEATER Print file 2123
top ]
17. CATEGORIES
  • B. Spectrum Calculations, Generation of Group Constants and Cell Problems

Keywords: cross sections, interpolation, reaction rates.