NESC0540 PACTOLUS/CLOTHO

1. NAME OR DESIGNATION OF PROGRAM:  PACTOLUS/CLOTHO

3. DESCRIPTION OF PROBLEM OR FUNCTION

PACTOLUS is a code for computing nuclear power costs using the discounted cash flow method. The cash flows are generated from input unit costs, time schedules and burnup data. CLOTHO calculates and communicates to PACTOLUS mass flow data to match a specified load factor history.

4. METHOD OF SOLUTION

Plant lifetime power costs are calculated using the discounted cash flow method.

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Maxima of -
40 annual time periods into which all costs and mass flows are       accumulated
20 isotopic mass flows charged into and discharged from the       reactor model

6. TYPICAL RUNNING TIME

For typical nuclear plants having a lifetime  of 30 years and between 50 and 200 charge-discharge fueling events,  a run time of 10 to 25 seconds can be expected.

7. UNUSUAL FEATURES OF THE PROGRAM

Although the PACTOLUS/CLOTHO code  is designed primarily for nuclear power plant cost analysis, by proper input of mass flows and unit costs any similar plant such as  a fossil-fueled power plant or a hydroelectric plant can be simulated. An option of PACTOLUS allows direct reading of mass flows of light-water reactors from a burnup tape provided by the ALTHAEA burnup code described in reference 4. Any similar burnup tape could  be used for any specific reactor design, or card input can be provided through CLOTHO.

8. RELATED AND AUXILIARY PROGRAMS

The power cost calculation in PACTOLUS/CLOTHO is a modified version of a technique developed by Royes Salmon of Oak Ridge National Laboratory and described in the report, A Procedure and a Computer Code (POWERCO) for Calculating the Cost of Electricity Produced by Nuclear Power Stations, ORNL-3944, June 1966.  See NESC Abstract 340.

10. REFERENCES

C.  H. Bloomster,  J.  H. Nail,  and  D. R.  Haffner,
PACTOLUS, A  Code for  Computing Nuclear  Power Costs,  BNWL-1169,
January 1970.
             J. H.  Nail, PACTOLUS, A  Code for  Computing Nuclear
Power Costs, Part 1, User's Manual, BNWL-429, June 1967.
             J. H. Nail, CLOTHO, A  Code for Communicating Reactor
Mass Balance Data to Reactor Economics Codes, BNWL-770, June 1968.
             E. T. Merrill, ALTHAEA Part 1, A One-dimensional Two-
group  Diffusion   Code  with  an  Effective   Four-group  Burnup,
BNWL-462, May 1971.
             R.  Salmon, Excerpted  Pages  from ORNL-4116,  August
1969.
             D. R. Haffner, Operation of the PACTOLUS/CLOTHO Code,
HEDL Memo, February 21, 1973.
             Selected   Pages   from  CSCX   RJE/CRJE   Reference,
E00003-02-00, Vol. 2.
             NTRAN I/O Routines Description, Excerpt from UP-3569,
Rev. 1.

11. MACHINE REQUIREMENTS

65K memory with drum storage of input data to speed up processing.

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:   CSCX.

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:

15. NAME AND ESTABLISHMENT OF AUTHOR

                 D. R. Haffner
                 Hanford Engineering Development Laboratory
                 Westinghouse Hanford Company
                 P. O. Box 1970
                 Richland, Washington  99352

File name	File description	Records
NESC0540_01.001	SOURCE PROGRAM + SAMPLE PROBLEM INPUT DATA	4432
NESC0540_01.002	SAMPLE PROBLEM PRINTED OUTPUT	698

File name	File description	Records
NESC0540_02.001	INFORMATION	8
NESC0540_02.002	CLOTHO SOURCE PROGRAM (F4)	565
NESC0540_02.003	CLOTHO SAMPLE PROBLEM INPUT DATA	311
NESC0540_02.004	CLOTHO DD CARDS	3
NESC0540_02.005	CLOTHO SAMPLE PROBLEM PRINTED OUTPUT	84
NESC0540_02.006	PACTOLUS MAIN PROGRAM (F4)	76
NESC0540_02.007	PACTOLUS SOURCE PROGRAM (F4)	5913
NESC0540_02.008	PACTOLUS SAMPLE PROBLEM INPUT DATA	16
NESC0540_02.009	PACTOLUS DD CARDS	2
NESC0540_02.010	PACTOLUS SAMPLE PROBLEM PRINTED OUTPUT	730
NESC0540_02.011	AUXILIARY-1 SOURCE PROGRAM (F4)	66
NESC0540_02.012	AUXILIARY-1 SAMPLE PROBLEM INPUT DATA	723
NESC0540_02.013	AUXILIARY-1 SAMPLE PROBLEM PRINTED OUTPUT	793
NESC0540_02.014	AUXILIARY-2 SOURCE PROGRAM (F4)	101
NESC0540_02.015	AUXILIARY-3 SOURCE PROGRAM (F4)	107
NESC0540_02.016	POWERCO MAIN PROGRAM (F4)	71
NESC0540_02.017	POWERCO SAMPLE PROBLEM INPUT DATA	36
NESC0540_02.018	POWERCO SAMPLE PROBLEM PRINTED OUTPUT	314