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NEA-0870 BISON.

BISON, 1-D Burnup and Transport in Slab, Cylindrical, Spherical Geometry

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1. NAME OR DESIGNATION OF PROGRAM:  BISON.
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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
BISON-1.5 NEA-0870/02 Arrived 18-AUG-2001

Machines used:

Package ID Orig. computer Test computer
NEA-0870/02 HITAC M-150 H
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3. DESCRIPTION OF PROBLEM OR FUNCTION

BISON-1.5 solves the one- dimensional Boltzmann transport equation for neutron and gamma-rays  and transmutation equations for fuel nuclides.
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4. METHOD OF SOLUTION

In the transport calculation stage the one- dimensional Boltzmann transport equation is solved by the discrete ordinates method. In the burnup calculation stage, transmutation equations for fuel nuclides are solved by Bateman's method. The neutron flux obtained in the transport calculation stage is used to  determine the transmutation rates in the burnup calculation stage. Both stages are repeated in tandem till the end of the burnup cycle.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

A 42-group neutron and 21-group gamma-ray cross section library is prepared in the code package. Core storage for array variables is dynamically allocated by the code, so there are no restrictions on the size of each array.
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6. TYPICAL RUNNING TIME

Running time depends on the problem size. It  takes about 2 hours to solve the sample problem included in the code package on HITAC-M150 H.
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7. UNUSUAL FEATURES OF THE PROGRAM:  None.
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8. RELATED AND AUXILIARY PROGRAMS

The BISON-1.5 code is a new version of the BISON code. The former differs from the latter in the support of adjoint calculations and data input by free format.
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9. STATUS
Package ID Status date Status
NEA-0870/02 18-AUG-2001 Masterfiled Arrived
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10. REFERENCES:
NEA-0870/02, included references:
- K. Furuta, Y. Oka, and S. Kondo:
  BISON-1.5: A One-Dimensional Transport and Burnup Calculation Code
  UTNL-R 203 (February 1987)
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11. MACHINE REQUIREMENTS:  IBM compatible machines with FORTRAN 77 compiler.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0870/02 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  HITAC VOS3 (Operating system like VMS on IBM machines).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

    The
clock routine should be patched to install the code on machines other than HITAC.
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15. NAME AND ESTABLISHMENT OF AUTHOR

          Kazuo Furuta, Shunsuke Kondo
          Nuclear Engineering Research Laboratory
          Faculty of Engineering, University of Tokyo, Japan

          Yoshiaki Oka
          Department of Nuclear Engineering
          University of Tokyo, Japan
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16. MATERIAL AVAILABLE
NEA-0870/02
source program   mag tapeBISON1.5, Fortran source code              SRCTP
test-case data   mag tapeJCL and sample input                       DATTP
test-case data   mag tapeSample printout                            DATTP
test-case data   mag tapeSample output of FT30 (plotting file)      DATTP
test-case data   mag tapeSample output of FT13                      DATTP
object program   mag tapeBison58 cross section library (BCD)        OBJTP
object program   mag tapeBCD to binary convertor for cross section  OBJTP
object program   mag tapeACIX burnup cross section library          OBJTP
test-case data   mag tapeSubset of ACIX for TH-U fuel cycle         DATTP
test-case data   mag tapeSubset of ACIX for U-PU fuel cycle         DATTP
test-case data   mag tapeSample response functions                  DATTP
report                   UTNL-R 203 (February 1987)                 REPPT
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17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: burnup, one-dimensional, transport theory.