DLC-0085 ZZ-FCXSEC.

1. NAME OR DESIGNATION OF PROGRAM:  FCXSEC.

3. DESCRIPTION OF PROBLEM OR FUNCTION


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  FORMAT: (a) & (b) AMPX
          (c) & (d) ANISN

  NUMBER OF GROUPS: (a) Fine-group 171 neutron and 36 gamma-ray
                    (b) Broad-group 22 neutron and 21 gamma-ray
                    (c) Broad-group microscopic (22n-21gamma)
                    (d) Broad-group macroscopic

NUCLIDES: Mixtures: H2O, Borated water, Concrete, D2O, Lithiu hydride, Boral, Dry air, Nitric acid, Uranium dioxide, SS304, UF6 TBP in dodecane, Sm2O3, Eu2O3, Gd2O3, Gd(NO3)3 in water, WB2, Spen fuel oxide, Thorium oxide, Uranium metal, Silver zeolite.
Individual materials: C, Na, Al, Fe, Zircaloy, Cd Nb, Mo, Pb, Be, Ti, V, Mn, Co, Cu, Sn, Ta.

  ORIGIN: VITAMIN-C

  WEIGHTING SPECTRUM:
From 1.1109+5 eV to 1.7333+7 eV -> 239Pu thermal fission
From 4.1399-1 eV to 1.1109+5 eV -> 1/E
From 1.0000-5 eV to 4.1399-1 eV -> Maxwellian

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FSXSEC is a collection of cross section libraries to be used for nuclear fuel cycle shielding calculations, generated from the pseudo-composition-independent VITAMIN-C cross section library:

(a) A composition-dependent self-shielded fine-group library with 171 neutron groups and 36 gamma groups, and a broad-group library with 22 neutron and 21 gamma groups for AMPX.

(b) A broad-group microscopic and a broad-group macroscopic library in ANISN format.

4. METHOD OF SOLUTION

To generate library (a), AMPX modules BONAMI, CHOX, and MALOCS were used. To generate library (b), AMPX modules NITAWL and AXMIX were used.

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:

6. TYPICAL RUNNING TIME:

NEA-DB executed the library conversion program on VAX-11/780. The following CPU times were found:
   1 minute  21 seconds to convert the macroscopic FCXSEC library;
   6 minutes 39 seconds to convert the microscopic FCXSEC library.

7. UNUSUAL FEATURES OF THE PROGRAM:

8. RELATED AND AUXILIARY PROGRAMS

AMPX modules BONAMI, CHOX, MALOCS NITAWL, and AXMIX were used to generate the cross section libraries.

10. REFERENCES

- "VITAMIN-C 171 Neutron, 36 Gamma-Ray Group Cross Sections in AMPX
  and CCCC Interface Formats for Fusion and LMFBR Neutronics"
  Documentation for RSIC's Data Library Collection DLC-41/VITAMIN-C
  May 2, 1978
- "AMPX-II Modular Code System for Generating Coupled Multigroup
  Neutron-Gamma-Ray Cross-Section Libraries from Data in ENDF
  Format"
  RSIC summary documentation for PSR-63/AMPX-II (November 1978)

- W.E. Ford III, C.C. Webster, B.R. Diggs, R.E. Pevey and A.G.Croff:
  FCXSEC: Multigroup Cross-Section Libraries for Nuclear Fuel Cycle
  Shielding Calculations.  ORNL/TM-7038  (May 1980)

11. MACHINE REQUIREMENTS:

The library conversion program runs on VAX-11/780 in 236,032 bytes of main storage.

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:

VMS-V3.4 (VAX-11/780).

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:

15. NAME AND ESTABLISHMENT OF AUTHOR

Contributed by: Radiation Safety Information Computational Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, U. S. A.
Developed by:   Oak Ridge National Laboratory, Oak Ridge, Tennessee, USA
                Battelle, Columbus Ohio, USA

File name	File description	Records
DLC0085_01.001	INFORMATION FILE	52
DLC0085_01.002	MICROSCOPIC X-SEC LIBRARY (FORMATTED)	44022
DLC0085_01.003	MACROSCOPIC X-SEC LIBRARY (FORMATTED)	8609
DLC0085_01.004	DECIMAL-BINARY CONVERSION PROGRAM	140
DLC0085_01.005	CONVERSION PROGRAM INPUT DATA	1
DLC0085_01.006	MACROSCOPIC X-SEC CONVERSION OUTPUT	116
DLC0085_01.007	MICROSCOPIC X-SEC CONVERSION OUTPUT	790