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IAEA0889 MCRAC/RBI.

MCRAC, In Core Fuel Management, Program of PFMP System

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1. NAME OR DESIGNATION OF PROGRAM:  MCRAC/RBI.
Multiple Cycle Reactor Analysis Code.
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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
MCRAC IAEA0889/01 Tested 07-NOV-1984
MCRAC IAEA0889/02 Tested 13-APR-1990
MCRAC/RBI IAEA0889/04 Tested 04-SEP-1992
MCRAC/RBI IAEA0889/05 Tested 22-MAR-1994

Machines used:

Package ID Orig. computer Test computer
IAEA0889/01 IBM 370 series IBM 3081
IAEA0889/02 IBM PC IBM PC
IAEA0889/04 DEC VAX series DEC VAX 8810
IAEA0889/05 IBM PC PC-80486
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3. DESCRIPTION OF PROBLEM OR FUNCTION

MCRAC is a two-dimensional, two-group diffusion code for global core analysis developed for in-core fuel management applications. It performs both nucleonic and economic analysis of PWR core over multiple cycles. MCRAC requires cross sections in the form of polynomials in burnup and in  soluble boron concentration, as generated by the PSU-LEOPARD code. The main features and options of MCRAC are:
  - x-y or r-z geometry
  - neutron diffusion approximation
  - 2-group or 1.5-group neutron diffusion model
  - multiple cycle power distribution and depletion calculation
  - multiple cycle fuel cost analysis
  - critical soluble boron concentration search
  - spatial power-dependent xenon-135 feedback modelling
  - control rod and burnable absorber simulation
  - search for LP with flat BOC power distribution
  - artificial ADDs
  - extensive printout control
  - variable dimensioning technique.
RBI version 90.1 of MCRAC is available for PC, IBM mainframe, and VAX. It offers:
  - compatibility with PSU-LEOPARD/RBI
  - the code is now completely in FORTRAN-77
  - timing routines for PC and VAX
  - more convenient input structure (ADD decks in a separate file)
  - fuel interchange option.
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4. METHOD OF SOLUTION

Core neutronics is modelled in two group, two dimensional diffusion approximation. The EQUIPOISE method is employed to solve the finite-difference discretized form. Programming techniques are based on the EXTERMINATOR-II code.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Variable dimensioning technique is used to store most of variables in just one huge array. The size of that array determines the allowed sum of dimensions of individual variable, i.e., the complexity of the problem. That array size may be easily increased depending on the available main memory.
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6. TYPICAL RUNNING TIME

Approximate running time for a complete cycle analysis (core quadrant modelled in X-Y geometry, 2-group model, 8
depletion steps, critical boron concentration search at each step, 19x19 mesh points, pointwise convergence criterion 0.0001):
A) PC with 80x87 coprocessor
46 min on 10 MHz PC-XT
22 min on 12 MHz PC-AT
9 min on 20 MHz PC-386
6 min on 25 MHz PC-386/Cache
B) PC-386 with 80387 coprocessor
4.5 min on 20 MHz PC-386
3.0 min on 25 MHz PC-386/Cache
C) IBM mainframe
2.5 min on IBM-4341 (IBM VS FORTRAN)
D) VAX
5.5 min CPU on VAX-11/750 (VAX-11 FORTRAN77)
IAEA0889/01
NEA-DB executed the test case on IBM 3081 in 19 seconds of CPU time.

IAEA0889/02
NEA-DB executed the test case on an IBM PC/AT micro- computer with 80287 co-processor in 40 minutes.

IAEA0889/05
NEA-DB ran the test case included in the package on a 66-MHz PC/80486 in one minute of elapsed time.
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7. UNUSUAL FEATURES OF THE PROGRAM

  - variable dimensioning technique
  - polynomial cross sections representation (ADDs)
  - multicycle neutronic/cost analysis
  - fuel interchange option.
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8. RELATED AND AUXILIARY PROGRAMS

Relation to previous version - The original IBM mainframe version of MCRAC was developed by Prof. S.H. Levine of Penn State University and released earlier to NEA DB (Package-ID IAEA 0889/01).
The RBI version offers:
  - source in FORTRAN77 standard
  - version for PC, IBM mainframe, and VAX
  - several new options.
Related programs - PSU-LEOPARD/RBI version 90.1.
PSU-LEOPARD/RBI and MCRAC/RBI form the computer code system PFMP/RBI (Penn State Fuel Management Package, RBI version). PSU-LEOPARD/RBI is used to prepare group constants for MCRAC/RBI.
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9. STATUS
Package ID Status date Status
IAEA0889/01 07-NOV-1984 Tested at NEADB
IAEA0889/02 13-APR-1990 Tested at NEADB
IAEA0889/04 04-SEP-1992 Tested at NEADB
IAEA0889/05 22-MAR-1994 Tested at NEADB
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10. REFERENCES

- S.H. Levine
  Module 5: In-Core Fuel Management, in Nuclear Fuel Cycle
  Educational Module Series (ed. N.D. Eckhoff),
  Kansas State University (1980).
- M.L. Tobias and T.B. Fowler
  The EQUIPOISE Method - A Simple Procedure for Group-Diffusion
  Calculations in Two and Three Dimensions
  Nucl. Sci. Eng., 12, 513 (1962).
- T.B. Fowler, M.L. Tobias, and D.R. Vondy
  EXTERMINATOR-II, A FORTRAN Code for Solving Multigroup Diffusion
  Equation in Two Dimensions
  ORNL-4078, Oak Ridge National Laboratory (1967).
- B.G. Petrovic
  In Core Fuel Management: PWR Core Calculations Using MCRAC,
  Lecture notes, Workshop on Reactor Physics Calculations for
  Applications in Nuclear Technology
  ICTP, Trieste (1990).
IAEA0889/01, included references:
- H.Y. Huang, J.P. Colletti, Z.H. Kodah and S.S. Kim:
  MCRAC - Multiple Cycle Reactor Analysis Code. User's Guide.
  315-497991  (July 20, 1981)
- In-Core Fuel Management Programs for Nuclear Power Reactors
  IAEA-TECDOC-314  (October 1984)
IAEA0889/02, included references:
- B.G. Petrovic, D. Pevec and S.H. Levine:
  MCRAC (RBI PC Version 89.4) Input Manual
  RBI-LP-1/90 (1990).
- MCRAC - PC Package Description (RBI PC Version 89.4)
IAEA0889/04, included references:
- B.G. Petrovic and D. Pevec:
  MCRAC/RBI Version 90.1 Use's Guide
  RBI-LP-N-12/90 (1990).
- In-Core Fuel Management Programs for Nuclear Power Reactors
  IAEA-TECDOC-314 (October 1984).
IAEA0889/05, included references:
- B.G. Petrovic and D. Pevec:
  MCRAC/RBI Version 90.1 Use's Guide
  RBI-LP-N-12/90 (1990).
- In-Core Fuel Management Programs for Nuclear Power Reactors
  IAEA-TECDOC-314 (October 1984).
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11. MACHINE REQUIREMENTS

A) About 480 KB of available (free) RAM memory required
Hard disk and mathematical coprocessor recommended.
B) About 480 KB of available (free) RAM memory and mathematical
coprocessor, NDP FORTRAN-386 and Phar Lap Tools required
Hard disk recommended.
C) About 600 KB of main memory
D) About 600 KB of main memory
IAEA0889/02
An IBM PC/AT microcomputer with 80287 math co-processor was used.

IAEA0889/05
NEA-DB used a DELL 466/L PC (80486 processor, 66 MHz, 8 Mbytes of RAM).
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA0889/01 FORTRAN+ASSEMBLER
IAEA0889/02 FORTRAN-77
IAEA0889/04 FORTRAN-77
IAEA0889/05 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

A) MS-DOS or PC-DOS on PC-XT/AT/386
B) MS-DOS or PC-DOS and Phar Lap Tools on PC-386
C) OS/VS, OS2/MVS, CMS, or similar on IBM mainframe
D) VMS on VAX
IAEA0889/02
MSDOS 3.20 with Microsoft FORTRAN Optimizing compiler,  version 4.01 was used.

IAEA0889/04
The program was implemented by NEA-DB on a VAX 8810 computer running under VMS version 5.4-2.

IAEA0889/05
The tests were performed under MS-DOS 6.0 with the MicroSoft compiler Version 5.1.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

- On PC-386, version B is about two times faster than version A, but   requires NDP FORTRAN-386 compiler and Phar Lap Tools.
- Timing routines are provided through FORTRAN calls in PC and VAX  version. To avoid subroutines in assembly language, no timing is  provided in IBM mainframe version (CPU accounting automatically   done by OS).
- It is possible to recompile and run MCRAC on a PC without   coprocessor, but the running time increases significantly.
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15. NAME AND ESTABLISHMENT OF AUTHOR

This code system has been included in the Coordinated Research Programme (CRP) on "Codes Adaptable to Small and Medium-Size Com- puters Available in Developing Countries for In-Core Fuel Manage- ment" of the International Atomic Energy Agency.

RBI Version 90.1 (A, B, C, D)
B.G. Petrovic, T. Smuc, D. Pevec, and D. Grgic
Ruder Boskovic Institute
Bijenicka c. 54, P.O. Box 1016
4100 Zagreb, Yugoslavia
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16. MATERIAL AVAILABLE
IAEA0889/01
File name File description Records
IAEA0889_01.003 Information File 51
IAEA0889_01.004 MCRAC SOURCE (CARD IMAGES) 4803
IAEA0889_01.006 ASSEMBLER ROUTINES (CARD IMAGES) 246
IAEA0889_01.008 JCL 76
IAEA0889_01.009 MCRAC TEST CASE INPUT DATA 737
IAEA0889_01.010 MCRAC TEST CASE PRINTED OUTPUT 704
IAEA0889/02
File name File description Records
IAEA0889_02.001 Information file 115
IAEA0889_02.002 Compile + link 8087/80287 version 1
IAEA0889_02.003 Run MCRAC test case 1
IAEA0889_02.004 MCRAC part 1 source (FORTRAN) 593
IAEA0889_02.005 MCRAC part 2 source (FORTRAN) 590
IAEA0889_02.006 MCRAC part 3 source (FORTRAN) 585
IAEA0889_02.007 MCRAC part 4 source (FORTRAN) 572
IAEA0889_02.008 MCRAC part 5 source (FORTRAN) 618
IAEA0889_02.009 MCRAC part 6 source (FORTRAN) 446
IAEA0889_02.010 MCRAC part 7 source (FORTRAN) 578
IAEA0889_02.011 MCRAC part 8 source (FORTRAN) 412
IAEA0889_02.012 MCRAC part 9 source (FORTRAN) 598
IAEA0889_02.013 MCRAC (.EXE file) 1435
IAEA0889_02.014 Library file 238
IAEA0889_02.015 Test case input data 42
IAEA0889_02.016 Test case output 1340
IAEA0889_02.017 DOS file-names 16
IAEA0889/04
File name File description Records
IAEA0889_04.001 Information file 47
IAEA0889_04.002 JCL and control information 6
IAEA0889_04.003 MCRAC/RBI FORTRAN source program 5047
IAEA0889_04.004 MCRAC/RBI sample problem input data 41
IAEA0889_04.005 MCRAC/RBI sample problem input ADD file 238
IAEA0889_04.006 MCRAC/RBI sample problem output 1286
IAEA0889/05
File name File description Records
IAEA0889_05.001 Information file 109
IAEA0889_05.002 FORTRAN source 164
IAEA0889_05.003 FORTRAN source 430
IAEA0889_05.004 FORTRAN source 590
IAEA0889_05.005 FORTRAN source 594
IAEA0889_05.006 FORTRAN source 572
IAEA0889_05.007 FORTRAN source 618
IAEA0889_05.008 FORTRAN source 446
IAEA0889_05.009 FORTRAN source 578
IAEA0889_05.010 FORTRAN source 412
IAEA0889_05.011 FORTRAN source 598
IAEA0889_05.012 Executable file 0
IAEA0889_05.013 Compile and link command 1
IAEA0889_05.014 Sample problem (input) 41
IAEA0889_05.015 Sample problem (input ADD file) 238
IAEA0889_05.016 Sample problem (output) 1323
IAEA0889_05.017 Command to run sample problem 1
IAEA0889_05.018 FORTRAN source 4999
IAEA0889_05.019 Compile and link command 1
IAEA0889_05.020 Sample problem (input) 41
IAEA0889_05.021 Sample problem (input ADD file) 238
IAEA0889_05.022 Sample problem (output) 1320
IAEA0889_05.023 Command to run sample problem 3
IAEA0889_05.024 DOS file-names 23
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17. CATEGORIES
  • C. Static Design Studies
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: burnup, criticality, depletion, fuel management, multiplication factors, neutron diffusion equation, power distribution, pwr reactors, r-z, steady-state conditions, two-group theory, x-y.