Computer Programs
NEA-1187 BOREAS.
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NEA-1187 BOREAS.

BOREAS, Nuclear and Thermohydraulic LWR Burnup Simulation

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1. NAME OR DESIGNATION OF PROGRAM:  BOREAS.
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2. COMPUTERS
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Program name Package id Status Status date
BOREAS NEA-1187/03 Tested 27-MAR-1990

Machines used:

Package ID Orig. computer Test computer
NEA-1187/03 CDC CYBER 180 CDC CYBER 830
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3. DESCRIPTION OF PROGRAM OR FUNCTION

BOREAS is a three-dimensional reactor core simulator based upon a nodal model. It is designed for  realistic nuclear and thermal-hydraulic simulation of the burnup cycle  of a light  water reactor  with a square  fuel lattice. A
separate auxiliary code REFUEL performs reloading operations.
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4. METHOD OF SOLUTION

One- and one-half-group nodal model for the reactor core. Simultaneous neutronic and thermal-hydraulic iterations using Jacobi, Gauss-Seidel or SOR methods. The Levy and Zuber-Findlay or Premoli-Francisco-Prina correlations are used for the void fraction calculation.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Maximum core dimen-  sions 250x25 = 6250 nodes and 13x26x25 (IxJxK). 5 bundle types, 9
fuel types, 5 channel types. May easily be extended if sufficient memory available.
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6. TYPICAL RUNNING TIME

About 10 CP seconds on the CDC CYBER 180 computer for test problem with 121x10 nodes.
NEA-1187/03
BOREAS ran at NEA-DB on a CDC CYBER 830 in 35.5 seconds of CPU time.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS

The program package includes the auxiliary code REFUEL for reloading operations.
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9. STATUS
Package ID Status date Status
NEA-1187/03 27-MAR-1990 Tested at NEADB
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10. REFERENCES:
NEA-1187/03, included references:
- R. Hoeglund:
  A Nodal Method of Calculating Power Distributions for LWR-Type
  Reactors with Square Fuel Lattices.
  VTT NEL Report 51  (June 1980)
- R. Hoeglund:
  Nea Data Bank Version of BOREAS.
  RFD-04/1988  (March 14, 1988)
- R. Hoeglund:
  BOREAS - A Reactor Core Simulation Code for Burnup Cycle Studies
  on Light Water Reactors with a Square Fuel Lattice:
  Report 1 - Methods of Solution (The Neutronic Model)
  REP-5/80  (April 23, 1980)
  Report 2 - Methods of Solution (The Thermohydraulic Model)
  REP-10/80 (August 5, 1980)
  Report 3 - Input Description
  REP-3/81  (April 27, 1981)
  Report 4 - Refuelling Code
  REP-7/81  (September 3, 1981)
  Report 5 - Supplementary Input Description
  REP-2/83  (January 17, 1983)
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11. MACHINE REQUIREMENTS:  About 260 000 octal words.
NEA-1187/03
To run the test case of BOREAS inclded in this package  on a CDC CYBER 830, 270,0200 (octal) words of main storage are required.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-1187/03 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  CDC CYBER 180-840 NOS 2.
NEA-1187/03
NOS 2.5.1 (CDC CYBER 830).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

     Randolph Hoeglund
     Technical Research Centre of Finland
     Nuclear Engineering Laboratory
     P.O.B. 169
     SF-OO181 HELSINKI
     FINLAND
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16. MATERIAL AVAILABLE
NEA-1187/03
File name File description Records
NEA1187_03.001 Information file 75
NEA1187_03.002 JCL and control information 22
NEA1187_03.003 CORDISP FORTRAN source 57
NEA1187_03.004 KTABLEP FORTRAN source 57
NEA1187_03.005 REFUEL FORTRAN source 830
NEA1187_03.006 REFUEL input data 28
NEA1187_03.007 BOREAS FORTRAN source 3710
NEA1187_03.008 BOREAS input data 94
NEA1187_03.009 KTABLEP printed output 102
NEA1187_03.010 REFUEL printed output 138
NEA1187_03.011 BOREAS printed output 1339
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17. CATEGORIES
  • C. Static Design Studies
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: LWR reactors, burnup, fuel management, multiplication factors, power distribution, three-dimensional.