1. NAME AND TITLE OF DATA LIBRARY

FSX96: Collection of Continuous Energy Cross Section Libraries for MCNP Based on JENDL 3.2, JENDL, Fusion File and Dosimetry File.

2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

MAKXSF: Fortran 77 code for converting cross sections to binary form.

3. CONTRIBUTOR

Japan Atomic Energy Research Institute, Tokai-mura, Naka-gun, Ibaraki-ken, 319-11 Japan.

4. HISTORICAL BACKGROUND AND INFORMATION

In 1988 the first version of FSXLIB was released in Japan. It included 17 nuclides based on JENDL-3PR2, ENDF/B-IV and ENDF/B-V. In 1990 the second version of FSXLIB was informally released in Japan. It included 68 nuclides and added 48 nuclides based on JENDL-3 (revision-0) to the first version. In 1992 FSXLIB-J3, which was based on JENDL-3 (revision-1), was released.

The FSX96 is a collection of continuous energy cross section libraries based on recent JENDL releases for use with MCNP. This collection includes FSXLIB-J3R2 based on JENDL-3.2 released in 1994, the FSXLIB-JFF library based on the JENDL Fusion File, and the FSXDOS-J3 library based on the JENDL Dosimetry File.

5. APPLICATION OF THE DATA

Both FSXLIB-J3 and FSXLIB-JFF are to be used for coupled neutron-photon transport calculations while FSXDOS-J3 is for calculation of dosimetry reaction rates with the CCC-200/MCNP4 code system.

6. SOURCE AND SCOPE OF DATA

A modified version of the NJOY 83/6 processing code was used to produce ACE type cross section data, and all 340 nuclides from JENDL-3 Revision-2 were processed for inclusion in FSXLIB-J3R2. The format conforms to the continuous energy neutron cross section table as defined in the MCNP4 manual. Gamma-ray production data are supplied for 66 nuclides in the expanded photon production format. The processing temperature of cross section is 300 K. The energy range for neutrons is 10-11 eV to 20 MeV.

All 82 nuclides in the JENDL Fusion File were processed with NJOY91.108/FNS to produce ACE type data for FSXLIB-JFF. Gamma-ray production data are supplied for 35 nuclides. The pointwise processing of the JENDL Dosimetry File was done with LINEAR and SIGMA1, then the MACROS code was used to produce the FSXDOS-J3 library.

7. DISCUSSION OF THE DATA RETRIEVAL PROGRAMS

MAKXSF, which is distributed with CCC-200/MCNP4B, is the program used to convert MCNP Type 1 data to Type 2 (binary).

8. DATA FORMAT AND COMPUTER

BCD card images; FACOM M-780 or any UNIX-based computer (D00190/MNYWS/00).

9. TYPICAL RUNNING TIME

The running time for MAKXSF depends on the size of library treated, and usually ranges from several seconds to several minutes.

10. REFERENCES

a. included in the documentation:

Fujio Maekawa, "FSX96 Collection of Continuous Energy Cross Section Libraries for MCNP Based on Japanese Evaluated Nuclear Data Libraries," Informal Paper, Fusion Neutronics Laboratory, JAERI (November 1996).

K. Kosako, N. Yamano, F. Maekawa, and Y. Oyama, "Production and Verification of the MCNP Cross Section Library FSXLIB-J3R2 Based on JENDL-3.2," (presented at the American Nuclear Society Radiation Protection & Shielding Topical Meeting, April 21-25, 1996, Falmouth, MA).

K. Kosako, "The Present Status of Cross Section Libraries," paper presented at the Third Specialist's Meeting on Nuclear Data for Fusion Reactors in Tokai, Japan, JAERI-Conf 96-005, pp. 55-62 (Nov. 1995).

K. Kosako, F. Maekawa, Y. Oyama, Y. Uno, and H. Maekawa, "FSXLIB-J3R2: A Continuous Energy Cross Section Library for MCNP Based on JENDL-3.2," JAERI-Data/Code 94- 020 (Dec. 1994).

b. background information:

T. Nakagawa, et. al., "Japanese Evaluated Nuclear Data Library, Version 3 Revision-2: JENDL-3.2," J. Nucl. Sci. Technol., 32, 1259 (1995).

J. F. Briesmeister (editor), "MCNP - A General Monte Carlo Neutron and Photon Transport," LA-12625-M (1993).

R. E. MacFarlane, D. W. Muir, and R. M. Boicourt, "The NJOY Nuclear Data Processing System," LA-9303-M (ENDF-324) (1982).

11. CONTENTS OF LIBRARY

Included are the referenced documents in 10.a, libraries, and xsdirfsx in a Unix compressed tar file, which is 168 MB, and is transmitted on either a CD-ROM or cartridge tape. The uncompressed ascii files are about 445 MB.

12. DATE OF ABSTRACT

February 1997.

KEYWORDS: BASED ON JENDL; EVALUATED NEUTRON CROSS SECTIONS; MCNP FORMAT; NEUTRON CROSS SECTIONS