**1. NAME AND TITLE**

BISON-C: One-Dimensional Discrete Ordinate Transport and Burnup Calculation
Code System. (**B**urnup of **Is**otopes and **On**e-Dimensional Transport.)

**AUXILIARY ROUTINE**

SIGC: Cross-section library processing code to prepare response functions and cross sections with self-shielding corrections for Bison-C.

XSCON: Format conversion code for multigroup cross section library for BISON, ANISN, MORSE library processing.

RESPL: Code for production of response functions from an ANISN-format neutron
transport library.

**DATA LIBRARIES**

BIS60.XSV: 42-group neutron cross section set for 60 nuclides obtained from JENDL-3.

AC22.IX: Burnup library.

BIS60.RSC: Response function file.

**2. CONTRIBUTOR**

Faculty of Physics and Nuclear Techniques, University of Mining and Metallurgy, Cracow,
Poland.

**3. CODING LANGUAGE AND COMPUTER**

Fortran 77; IBM RS/6000 and HP (C00659/MNYWS/00).

**4. NATURE OF PROBLEM SOLVED**

BISON-C calculates time-dependent functions and parameters of a nuclear system with external source including burnup, k-effective, neutron and gamma-ray flux, neutron reaction rates, and system power in complex heterogeneous blanket structures. It is applicable for research of transmutations in accelerator driven subcritical systems.

BISON1.5 was developed in the 1980's by K. Furuta, Y. Oka and S. Kondo at Tokyo
University on the basis of CCC-254/ANISN, a one-dimensional discrete ordinates transport code,
while applying the linear chain method for solution of nuclide production-depletion equations known
as Bateman's equations. Required libraries of burnup chain data, decay data, and neutron cross
sections were based on JENDL-2 and ENDF-B/IV, and the code itself did not allow for either fission
product transmutations or application to more complex heterogenous systems. The cross section
library processing system that includes codes XSCON, RESPL and SIGC were developed by
J.Cetnar. These codes were used to upgrade the library based on JENDL-3 files and were used with
BISON1.5 for research in transmutations of actinides in fusion-fission hybrid systems. BISON-C
was developed from BISON1.5 at The University of Mining and Metallurgy in Cracow, Poland (the
"C" extension of the code name stands for Cracow). It extends the original code features by
providing burnup calculation for fission products and allows consideration of more complex systems
and processes. It also provides differentiation of time steps and step-dependent burnup
normalization to the required thermal power. The new burnup library additionally contains the
fission product burnup chain and fission yields for actinides which were prepared from ENDF-B/VI
data files.

**5. METHOD OF SOLUTION**

The one-dimensional transport equation is solved using the discrete ordinates method; ANISN provided subroutines for this process. For complex heterogeneous blanket structures, provides for self-shielding cross sections by zone. Bateman's method is adopted to solve production-depletion equations for burnable nuclides. Burnup calculation is carried out by performing these two processes iteratively.

**6. RESTRICTIONS OR LIMITATIONS**

The one-dimensional code uses multigroup cross sections which require correction for self-shielding effects in case of strong neutron absorption. The introduced fission yield is nuclide
dependent but not incident neutron-energy dependent.

**7. TYPICAL RUNNING TIME**

Running time depends on input specifications. The test case that is made of 140 mesh points
and 3 time steps in cylindrical geometry requires 25 minutes of CPU time on an IBM RS/6000
computer.

**8. COMPUTER HARDWARE REQUIREMENTS**

BISON-C runs on IBM RS/6000 and HP workstations and requires less than 20 MB of disk
space.

**9. COMPUTER SOFTWARE REQUIREMENTS**

BISON-C runs under Unix operating systems and requires a Fortran 77 compiler.

**10. REFERENCES**

**a. Included in the documentation:**

J. Cetnar and P. Gronek, "BISON-C Upgraded One-Dimensional Transport and Burnup Calculation Code for Unix System," INT271/I (1997).

J. Cetnar, "Input Specifications for Running SIGC, XSCON and RESPL," Informal Notes
(1997).

**b. Background information:**

K. Furuta, Y. Oka, and S. Kondo, "BISON1.5: A One-Dimensional Transport and Burnup
Calculation Code," (CCC-464) Informal Notes (February 1987).

**11. CONTENTS OF CODE PACKAGE**

Included are the document referenced in (10.a) and two DS/HD diskettes which contain the
source code, sample problem, and BISON data libraries written in a compressed Unix tar file.

**12. DATE OF ABSTRACT**

July 1998.

**KEYWORDS: ** ONE-DIMENSION; BURNUP; DISCRETE ORDINATES; ISOTOPE
INVENTORY; MULTIGROUP; NEUTRON; GAMMA-RAY;
ACTINIDES; WORKSTATION