IAEA1190 BRETISLAV. OLDRICH.

BRETISLAV,OLDRICH, Neutron Diffusion in Hexagonal Geometry for WWER Critical Fuel Assemblies

NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES

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1. NAME OR DESIGNATION OF PROGRAM: BRETISLAV. OLDRICH.

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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
OLDRICH	IAEA1190/01	Tested	21-NOV-2002
BRETISLAV	IAEA1190/02	Tested	05-DEC-2002

Machines used:

Package ID	Orig. computer	Test computer
IAEA1190/01	ES-1040	PC Pentium III
IAEA1190/02	ES-1040	PC Pentium III

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3. DESCRIPTION OF PROGRAM OR FUNCTION

BRETISLAV: The diffusion equation in the difference form is solved in two-dimensional hexagonal geometry. The program is applied to criticality calculations in WWER reactors.
OLDRICH: Geometry data generator for BRETISLAV.

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4. METHOD OF SOLUTION:

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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 OF THE PROGRAM:

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8. RELATED AND AUXILIARY PROGRAMS:

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9. STATUS

Package ID	Status date	Status
IAEA1190/01	21-NOV-2002	Tested at NEADB
IAEA1190/02	05-DEC-2002	Tested at NEADB

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10. REFERENCES:

IAEA1190/01, included references:

- V. Lelek:
Program OLDRICH for the Generation of the Hexagonal Net
UJV 9268 R.A (January 1991).

IAEA1190/02, included references:

- V. Lelek:
Program BRETISLAV for Reactor Calculations in Hexagonal Geometry
UJV 9269 R.A (January 1991).

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11. MACHINE REQUIREMENTS:

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12. PROGRAMMING LANGUAGE(S) USED

Package ID	Computer language
IAEA1190/01	FORTRAN
IAEA1190/02	FORTRAN

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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:

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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:

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15. NAME AND ESTABLISHMENT OF AUTHORS

               Vladimir Lelek
               Institute for Nuclear Research
               Rez, Czechoslovakia

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16. MATERIAL AVAILABLE

IAEA1190/01

source program   mag tapeOLDRICH Source Program (OLDR27GG)          SRCTP
test-case data   mag tapeTest Problem Input Data (DATOLDR)          DATTP
test-case data   mag tapeJob Control Informations to run (JOBOLDR)  DATTP
test-case output mag tapeTest Problem Printed Output (OLDRPRNT)     OUTTP
report                   UJV 9268 R.A (January 1991).               REPPT
source program
test problem input data
Job control information to run
test problem printed output

IAEA1190/02

source program   mag tapeBRETISLAV Source Program (BRET87LG)        SRCTP
test-case data   mag tapeTest Problem Input Data (DATBRET)          DATTP
test-case data   mag tapeJob Control Informations to run (JOBBRET)  DATTP
test-case output mag tapeTest Problem Printed Output (BRETPRNT)     OUTTP
report                   UJV 9269 R.A (January 1991).               REPPT
source program
Test problem input data
job control information to run
test problem printed output

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17. CATEGORIES

C. Static Design Studies

Keywords: criticality, hexagonal, neutron diffusion equation.