last modified: 19-MAY-1983 | catalog | categories | new | search |

NEA-0617 FAPMAN-IC.

FAPMAN-IC, LWR Fuel Cost Analysis with Program ORSIM Interface

top ]
1. NAME OR DESIGNATION OF PROGRAM:  FAPMAN-IC.
top ]
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
FAPMAN-IC NEA-0617/01 Tested 19-MAY-1983

Machines used:

Package ID Orig. computer Test computer
NEA-0617/01 IBM 370/168 IBM 370/168
top ]
3. DESCRIPTION OF PROBLEM OR FUNCTION

FAPMAN-IC is a set of sub- routines that calculates the nuclear fuel cost and associated incremental fuel cost of LWR (Light Water moderated Reactors) power  stations. It is based on the same FAPMAN model as FAPMAN-8 program,  but with the interfacing capabilities to the more overall system planning model like ORSIM. The major parameters on the interface are plant operating schedule, demand electric power, plant thermal efficiency, annual discount factor and plant rating power, that must be provided on calling the subroutine. The major return parameters are cycle fuel cost and cycle incremental fuel cost.
top ]
4. METHOD OF SOLUTION:  Iterative Linear Programming.
top ]
5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Though fuel loading  is represented in terms of fuel batches having various shuffling histories, the fuel assembly allocation within a region is not dealt with.
top ]
6. TYPICAL RUNNING TIME

Running time mainly depends on the number of  the constraints in Linear Programming as well as the convergence criteria. Typical CPU time is 1 to 4 minutes per one iteration for FACOM 230/28, whose speed is estimated as about 1/50 of that of IBM 370/168. An incremental cost calculation for typical PWR of 7 refueling cycles requires about 80 minutes.
top ]
7. UNUSUAL FEATURES OF THE PROGRAM:
top ]
8. RELATED AND AUXILIARY PROGRAMS

Two subprograms for interfacing FAPMAN-IC to ORSIM code. Test driver (main program) calls FAPMAN-IC through these interfacing subprograms.
NEA-0617/01
ORSIM
top ]
9. STATUS
Package ID Status date Status
NEA-0617/01 19-MAY-1983 Tested at NEADB
top ]
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, to be published in
  Nucl. Technol. (1980);
  Part III:  Incremental Cost Study, to be published in Nucl.
  Technol. (1980).
- T. Hoshino:
  FAPMAN-8, An Operation Planning Aid for LWR Power Stations
  Tech. Rep. Inst. Atom. Energy Kyoto Univ., No. 178 (1979).
- T. Hoshino:
  FAPMAN-IC, A Program Module Calculating the Incremental Fuel Cost
  of LWR Power Stations, to be published in Tech.
  Rep. Inst. Atom. Energy Kyoto Univ. (1980).
top ]
11. MACHINE REQUIREMENTS

About 100 K bytes for common data area and about 300 K bytes for program part. Disc pack memory of about 360 K bytes for 19 data files.
top ]
12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0617/01 FORTRAN-IV
top ]
13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  FACOM 230/28 BOS/VS Operating System.
top ]
14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
top ]
15. NAME AND ESTABLISHMENT OF AUTHOR

          Tsutomu Hoshino
          Institute of Atomic Energy
          Kyoto University
          Uji, Kyoto 611
          Japan.
top ]
16. MATERIAL AVAILABLE
NEA-0617/01
File name File description Records
NEA0617_01.003 FAPMAN-IC INFORMATION FILE 84
NEA0617_01.004 FAPMAN-IC SOURCE (FORTRAN-4) 5741
NEA0617_01.005 ORSIM DRIVER SOURCE (FORTRAN-4) 302
NEA0617_01.006 RANDOM NUMBER GENERATOR (ASSEMBLER) 25
NEA0617_01.007 FAPMAN-IC JCL 59
NEA0617_01.008 FAPMAN-IC INPUT FOR TEST CASE 199
NEA0617_01.009 FAPMAN-IC OUTPUT OF TEST CASE 2039
top ]
17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: BWR reactors, LWR reactors, cost, fuel management, mathematical models, optimization, power plants, pwr reactors.