last modified: 11-JUL-2002 | catalog | categories | new | search |

DLC-0210 ZZ-CANDULIB-AECL.

ZZ CANDULIB-AECL, Burnup-Dependent ORIGEN-S Cross-Section Libraries for CANDU Reactor Fuels

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1. NAME OR DESIGNATION OF PROGRAM:  ZZ-CANDULIB-AECL.
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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
ZZ-CANDULIB-AECL DLC-0210/01 Tested 11-JUL-2002

Machines used:

Package ID Orig. computer Test computer
DLC-0210/01 Many Computers PC Pentium III 500
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3. HISTORICAL BACKGROUND AND INFORMATION


%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%  
                        * 28-element fuel cross-section library *
FORMAT: Designed for use with the ORIGEN-S isotope generation and depletion code.
NUMBER OF GROUPS:
MATERIALS: Co, Ge, As, Se, Br, Kr, Rb, Sr, Y, Zr, Nb, Mo, Tc, Ru, Rh, Pd, Ag, Cd, In, Sn, Sb, Te, I, Xe, Cs, Ba, La, Ce, Pr, Nd, Pm, Sm, Eu, Gd, Tb, Dy, Ho, Er, Lu, Ta, W, Re, Au, Th, Pa, U, Np, Pu, Am, Cm
TEMPERATURES:
ORIGIN: ENDSF, ENDF/B-IV, -V and -VI
WEIGHTING SPECTRUM: determined using WIMS-AECL transport code.


                        * 37-element fuel cross-section library *
FORMAT: Designed for use with the ORIGEN-S isotope generation and depletion code.
NUMBER OF GROUPS:
MATERIALS: Co, Ge, As, Se, Br, Kr, Rb, Sr, Y, Zr, Nb, Mo, Tc, Ru, Rh, Pd, Ag, Cd, In, Sn, Sb, Te, I, Xe, Cs, Ba, La, Ce, Pr, Nd, Pm, Sm, Eu, Gd, Tb, Dy, Ho, Er, Lu, Ta, W, Re, Au, Th, Pa, U, Np, Pu, Am, Cm
TEMPERATURES:
ORIGIN: ENDSF, ENDF/B-IV, -V and -VI
WEIGHTING SPECTRUM: determined using WIMS-AECL transport code.
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%

In 1995, updated ORIGEN-S cross-section libraries were created as part of a program to upgrade and standardize the computer codes and nuclear data employed for used fuel characterization.  This effort was funded through collaboration between Atomic Energy of Canada Limited and the Canadian Nuclear Power Utilities, under the CANDU Owners Group (COG).  The updated cross sections were generated using the WIMS-AECL lattice code and ENDF/B-V and -VI based data to provide cross section consistency with reactor physics codes.

APPLICATION OF THE DATA -

The libraries in this data collection are designed for characteriting used fuel from CANDU pressurized heavy water reactors.  Two libraries are provided:  one for the standard 28-element fuel bundle design, the other for the 37-element fuel bundle design.  Thelibraries were generated for typical reactor operating conditions.  The libraries are designed for use with the ORIGEN-S isotope generation and depletion code.
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4. SOURCE AND SCOPE OF DATA

The CANDU libraries are updated with cross sections from a variety of different sources.  Capture and fission cross sections were obtained from collapsed 89-group ENDF/B-V and -VI data from the WIMS-AECL lattice code.  Other reaction cross sections were obtained from the SCALE 27-group ENDF/B-IV data.  In all, cross sections for more than 200 important actinides and fission products were updated with burnup-dependent data.  The source of the nuclear decay data and cross sections not updated were the base ORIGEN-S libraries distributed with the SCALE 4.2 code package.

The burnup-dependent cross sections were generated using eight burnup intervals that extend up to a burnup of approximately 12000 MWd/MgU.  The cross sections for each interval are stored in positions on the ORIGEN-S library and are accessed by referencing the position number.  The burnup values associated with each position are listed below.  They are the same for both the 37-element and 28-element libraries.

Library    Burnup
Position  (MWd/MgU)
1          240
2          720
3         1440
4         2880
5         4800
6         6720
7         8640
8        10560
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
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6. TYPICAL RUNNING TIME
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7. UNUSUAL FEATURES
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8. RELATED OR AUXILIARY PROGRAMS
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9. STATUS
Package ID Status date Status
DLC-0210/01 11-JUL-2002 Screened
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10. REFERENCES
DLC-0210/01, included references:
- I. C. Gauld, P. A. Carlson, and K. A. Litwin:
Production and Validation of ORIGEN-S Cross-Section Libraries for
CANDU Ractor Fuel Studies
Atomic Energy of Canada Limited report RC-1442 (COG-I-95-200), October 1995.
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11. HARDWARE REQUIREMENTS

The libraries are distributed in a card-image format for platform compatibility.  They must be converted to binary library format using the OSBICO utility of SCALE. (See example of input included in the REAME file).
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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13. SOFTWARE REQUIREMENTS
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHORS

Contributed by:
                Radiation Safety Information Computational Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, U. S. A.

Developed by:   Atomic Energy of Canada Limited
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16. MATERIAL AVAILABLE
DLC-0210/01
arpdata.txt Input
Bruce684.inp Input file
Bruce685.out Output file
candu28e.data Input file
candu37e.data Input file
osbire.inp Input file
Readme Readme file
DLC_210_1.PDF Documentation in pdf format
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17. CATEGORIES
  • Z. Data.

Keywords: burnup, cross sections, data library, heavy water moderated reactors.