last modified: 01-JUN-1967 | catalog | categories | new | search |

NEA-0176 HETERO.

HETERO, Flux and Power Distribution in Thermal Reactor by 3-D, 2 Group Line Source Sink Method

top ]
1. NAME OR DESIGNATION OF PROGRAM:  HETERO.
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
HETERO NEA-0176/01 Tested 01-JUN-1967

Machines used:

Package ID Orig. computer Test computer
NEA-0176/01 IBM 7090 IBM 7090
top ]
3. NATURE OF PHYSICAL PROBLEM SOLVED

The line source-sink method is used to calculate the flux and power distribution in a thermal reactor. 3 dimensions and 2 energy groups are used. Possibilities for burnup calculations and fuel movements are incorporated.
top ]
4. METHOD OF SOLUTION

The eigenvalue (the reactivity) and the eigenvector are solved by direct iteration.
top ]
5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Maximum number of element groups (n) - 150
maximum number of Fourier components (m) - min (64, 1500/n).
top ]
6. TYPICAL RUNNING TIME:  Depends strongly on the problem type.
top ]
7. UNUSUAL FEATURES: UNUSUAL FEATURES OF THE PROGRAM
top ]
8. RELATED OR AUXILIARY PROGRAMS: RELATED AND AUXILIARY PROGRAMS
top ]
9. STATUS
Package ID Status date Status
NEA-0176/01 01-JUN-1967 Tested at NEADB
top ]
10. REFERENCES

- A. Jonsson, G. Naeslund:
  Description of Heterogeneous Programmes for Macroscopic Reactor Calculations
  Part V.3. HETERO. Internal report RFN-226/RFR-603.
top ]
11. MACHINE REQUIREMENTS:  32k store, 9 tape units.
top ]
12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0176/01 FORTRAN-IV
top ]
13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED:  IBJOB.
top ]
14. ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:  Easily converted to IBM 7090 and GE 625.
top ]
15. NAME AND ESTABLISHMENT OF AUTHOR

G. Naeslund
                                   AB Atomenergi
                                   Box 43041
                                   Stockholm 43
                                   Sweden
top ]
16. MATERIAL AVAILABLE
NEA-0176/01
File name File description Records
NEA0176_01.001 SOURCE & DATA F4 V13 2675
NEA0176_01.002 OUTPUT 441
top ]
17. CATEGORIES
  • C. Static Design Studies
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: burnup, eigenvalues, eigenvectors, fuel elements, iterative methods, neutron flux, power distribution, thermal reactors, three-dimensional, two-group.