1. NAME AND TITLE

DETAN 95: Code System to Calculate Spectrum-Averaged Cross Sections and Detector Responses in Neutron Spectra.

DATA LIBRARIES

ENDF/B-V Dosimetry File (included in package)

2. CONTRIBUTOR

National Institute of Standards and Technology, Gaithersburg, Maryland.

3. CODING LANGUAGE AND COMPUTER

FORTRAN 77, CRAY Y-MP; UNIX, WORKSTATIONS; PC (P00361/MNYCP/00).

4. NATURE OF PROBLEM SOLVED

DETAN 95 multiplies an arbitrary neutron spectrum by an arbitrary energy-dependent neutron detector cross section or response function and integrates over energy to determine a spectrum-averaged cross section or response.

5. METHOD OF SOLUTION

DETAN 95 accepts an input neutron spectrum as a tabulated group spectrum or in one of several analytical forms. The code converts the spectrum into a fine-group tabulation. For neutron dosimetry cross sections, the tabulation is made in 625 groups; for other detector functions, the number of fine groups in the spectrum may be determined by the number of groups in the input detector function. The output gives either spectrum-averaged cross sections for a number of detector functions, or a detailed spectrum and response function for a specific detector response. The output energy group structure is specified by the user.

6. RESTRICTIONS OR LIMITATIONS

None noted.

7. TYPICAL RUNNING TIME

Runtimes vary but generally cases run in a few seconds.

8. COMPUTER HARDWARE REQUIREMENTS

DETAN 95 runs on many computers.

9. COMPUTER SOFTWARE REQUIREMENTS

The PC version of DETAN was tested at RSIC on a Northgate 486/66 running MS Windows 95 using MS FORTRAN v5.1 and Lahey F77L3-EM/32 v5.1 An executable created with Lahey is included.

The Unix version of DETAN was tested at RSIC on the machines listed below:

IBM RS/6000 running AIX 3.2.5 using IBM XL FORTRAN v3.2.2.3

DEC Alpha 3000/300 running Digital Unix 3.2d using DEC FORTRAN 77 v3.8

Sun Sparc 20 running Solaris 2.4 using Sun FORTRAN 77 v2.0

10. REFERENCES

C. M. Eisenhauer, "DETAN 95: Computer Code for Calculating Spectrum-Averaged Cross Sections and Detector Responses in Neutron Spectra," NISTIR 5622 (March 1995).

C. M. Eisenhauer, "DETAN 96: Documentation of Interactive Code for PC (June 1996).

11. CONTENTS OF CODE PACKAGE

Included are the referenced documents and one DS/HD 3.5" diskette (1.44MB) written in DOS format containing the source code: 625-group ENDF/BV dosimetry cross sections; sample input spectra, detector responses, and energy group structures; and sample problem input and output.

12. DATE OF ABSTRACT

June 1996.