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NEA-0693 FAPMAN-ORSIM.

FAPMAN-ORSIM, General Cost Optimization for System of Nuclear Power Plants

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1. NAME OR DESIGNATION OF PROGRAM:  FAPMAN-ORSIM.
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2. COMPUTERS
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Program name Package id Status Status date
FAPMAN-ORSIM NEA-0693/01 Tested 01-FEB-1984

Machines used:

Package ID Orig. computer Test computer
NEA-0693/01 IBM 3081 IBM 3081
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3. DESCRIPTION OF PROBLEM OR FUNCTION

The overall optimization is made for the power generating cost in the power system including several nuclear stations. FAPMAN-IC subroutines developed earlier were combined with the system integration model ORSIM, replacing the nuclear unit model originally implemented in the ORSIM code. The economic load dispatching is carried out in the ORSIM model following the loading order rule, and the power level, constant power days, refueling outage days, thermal efficiency and annual discount factor are transferred from ORSIM to FAPMAN-IC subroutines, where the cycle fuel cost and cycle incremental cost are calculated  and taken back to the ORSIM model. The optimization continues with changing the loading order, until the discounted power cost converges.
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4. METHOD OF SOLUTION

Iterative linear programming and sensitivity analysis in FAPMAN-IC part; probabilistic simulation technique and dynamic programming in ORSIM part.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:  Restrictions follow  those in FAPMAN-IC and ORSIM.
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6. TYPICAL RUNNING TIME

It took about 7 hours (CPU time) for the sample problem shown in the report (ORNL-TM-4506) with NPTS=3, where 11 nuclear units are all PWR type with 2-region fuel loading.
The Gibson-mix averaged computation time of FACOM M150F is estimated to be 2 micro-seconds.
NEA-DB executed part of the test case included in the package on IBM 3081. An extrapolation to full execution gives an estimated execution time of about 25 minutes.
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7. UNUSUAL FEATURES OF THE PROGRAM

FAPMAN part of the code requires extensive data file operation as the earlier FAPMAN version does, though they could be removed on a larger machine.
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8. RELATED AND AUXILIARY PROGRAMS:  FAPMAN-8, FAPMAN-IC (see Item 14).
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9. STATUS
Package ID Status date Status
NEA-0693/01 01-FEB-1984 Tested at NEADB
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10. REFERENCES

- T. Hoshino:
  "Optimum Fuel Loading and Operation Planning for Light Water
  Reactor Power Stations,
  Part   I: Pressurized Water Reactor Case Study", Nucl. Technol.
            Vol. 39, pp. 46-62 (1978);
  Part  II: Boiling Water Reactor Case Study", Nucl. Technol.,
            Vol. 47, pp. 421-435 (1980);
  Part III: Incremental Cost Study", Nucl. Technol., Vol. 47,
              pp. 436-443 (1980).
- T. Hoshino:
  "FAPMAN-8, An Operation Planning Aid for LWR Power Stations"
  Tech. Repts. Inst. Atom. Energy Kyoto Univ., No. 178 (1979).
- J. C. Turnage, B.E. Prince, D.S. Joy and L.L. Bennett:
  "The Oak Ridge System Integration Model (ORSIM) for Optimization
  of Utility Generation Planning"
  ORNL-TM-4506, Oak Ridge National Laboratory (1975).
NEA-0693/01, included references:
- T. Hoshina:
  "FAPMAN-IC, A Program Module Calculating the Incremental Fuel Cost
  of LWR Power Stations"
  ISSN 0372-1043 (March 1980).
- B.E. Prince and J.C. Turnage:
  "Use of Incremental Energy Costs and Loading Order Rules in the
  ORSIM Procedure for Midrange Optimization of Electric Utility
  Operations"
  ORNL-TM-4507 (October 1975).
- T. Hoshino:
  "How to Use FAPMAN-ORSIM"
  (December 9, 1980).
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11. MACHINE REQUIREMENTS

About 800 kbytes (virtual) storage area with  20 data files.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0693/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

FACOM OS IV/F2.
The test case was run by NEA-DB using MVS-SP (IBM 3081) with the FORTRAN-H-EXTENDED compiler.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

The earlier version FAPMAN-IC has been improved and revised, so that the FAPMAN subroutines of the present version should replace the earlier FAPMAN-IC subroutine modules.
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15. NAME AND ESTABLISHMENT OF AUTHOR

          Tsutomu Hoshino
          Institute of Atomic Energy
          Kyoto University
          Uji
          Kyoto 611
          Japan
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16. MATERIAL AVAILABLE
NEA-0693/01
File name File description Records
NEA0693_01.003 FAPMAN-ORSIM INFORMATION FILE 161
NEA0693_01.004 ORSIM SOURCE (CARD IMAGES) 3777
NEA0693_01.006 INTERFACE SOURCE (CARD IMAGES) 234
NEA0693_01.007 FAPMAN-IC SOURCE (CARD IMAGES) 5592
NEA0693_01.009 IFLD SOURCE (ASSEMBLER) 57
NEA0693_01.010 JCL FOR TEST CASE 126
NEA0693_01.011 INPUT DATA FOR TEST CASE 1102
NEA0693_01.012 OUTPUT OF TEST CASE 22619
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17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: LWR reactors, economics, fuel management, linear programming, optimization, power plants, power reactors, reactor operation.