Computer Programs
NESC0683 NUFUEL
last modified: 01-MAY-1978 | catalog | categories | new | search |

NESC0683 NUFUEL

NUFUEL, Conditions for Power Production, U Fuel, Pu Recycle and Reprocessing

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1. NAME OR DESIGNATION OF PROGRAM:  NUFUEL
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2. COMPUTERS

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Program name Package id Status Status date
NUFUEL NESC0683/01 Tested 01-MAY-1978

Machines used:

Package ID Orig. computer Test computer
NESC0683/01 IBM 370 series IBM 370 series
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3. DESCRIPTION OF PROBLEM OR FUNCTION

Given a forecast of nuclear electric generating capacity,it is important to know the consequent  time-related materials and services required to support it. These requirements depend on a number of parameters such as reactor types, plant operating capacity factor, expected availability of spent fuel reprocessing, policies concerning plutonium utilization (as breeder  fuel and LWR recycle). These and other conditions are simulated by NUFUEL which calculates and prints annual requirements for separative work and uranium related to a schedule of nuclear plant additions. Related fuel cycle quantities such as plutonium production and requirements, requirements for conversion to UF(6), for fuel fabrication, and for spent fuel reprocessing are also calculated and reported on a real-time basis.
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4. METHOD OF SOLUTION

Besides a schedule of plant additions by reactor type, reactor characteristics and fuel cycle data are needed as input data. They are provided for several common reactor types. Calculations assume that uranium enrichment plants approximate ideal cascade conditions and that the supporting facilities are available  when needed. A spent fuel reprocessing capability limitation feature which delays the reuse of uranium and plutonium from spent fuel until it can be reprocessed may be used. Recycling plutonium to light water reactors and simultaneously providing for other plutonium uses including breeder reactor fuel is an optional feature. Calculations are made for each individual reactor. Materials and process requirements are time-phased by quarter-years  according to assumed lead times and placed into accumulating arrays. The results of these accumulations are printed in the form of a report on an annual basis, either by calendar years or by fiscal years or both.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Array dimensions limit the forecasting to periods of 30 years at a time.
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6. TYPICAL RUNNING TIME

About 1.5 minutes are required to execute the sample problem on the IBM370/165 Model 2.
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7. UNUSUAL FEATURES OF THE PROGRAM

NUFUEL has been in use for a number of years for calculating materials requirements related to the Department of Energy nuclear power forecasts reported in the WASH-1139 document series.
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8. RELATED AND AUXILIARY PROGRAMS:
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9. STATUS
Package ID Status date Status
NESC0683/01 01-MAY-1978 Tested at NEADB
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10. REFERENCES

- Notes on  WASH-1348 and  Computer Program  NUFUEL-#4,
  (July 5, 1977).
- Artha Jean Snyder,
  Methods of Calculating U-235 Outputs and Charges by Use of Ideal
  Cascade Theory
  TID-8522 (February 1960).
- W.H. McVey, E.H. Davidson and G.E. McTigue,
  Calculating U-235 Outputs and Charges
  TID-8539 (June 30, 1963).
NESC0683/01, included references:
- Artha Jean Snyder:
  Computer Program NUFUEL for Forecasting Nuclear Fuel Requirements
  and  Related  Quantities
  WASH-1348 (October 1974).
- Notes on WASH-1348 and Computer Program NUFUEL-#2
  (July 31, 1975).
- Notes on WASH-1348 and Computer Program NUFUEL-#3
  (January 1, 1976).
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11. MACHINE REQUIREMENTS

The program requires 350K bytes to compile, 340K bytes to execute.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NESC0683/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:   OS/370 MVT.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHOR

                 Artha Jean Snyder
                 Division of Nuclear Energy Programs
                 U. S. Department of Energy
                 Washington, D.C.  20545
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16. MATERIAL AVAILABLE
NESC0683/01
File name File description Records
NESC0683_01.001 INFORMATION 2
NESC0683_01.002 SOURCE PROGRAM (F4,EBCDIC) 2824
NESC0683_01.003 DD CARDS FOR THE EXECUTION 72
NESC0683_01.004 SAMPLE PROBLEM INPUT DATA 443
NESC0683_01.005 SAMPLE PROBLEM PRINTED OUTPUT 3227
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17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: enrichment, fabrication, forecasting, fuel cycle, nuclear power plants, plutonium, reprocessing, uranium.