last modified: 14-FEB-1990 | catalog | categories | new | search |

IAEA0929 RICANT.

RICANT, Neutron Transport in X-Y Geometry for Isotropic Scattering

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1. NAME OR DESIGNATION OF PROGRAM:  RICANT.
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2. COMPUTERS
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Program name Package id Status Status date
RICANT IAEA0929/01 Tested 14-FEB-1990

Machines used:

Package ID Orig. computer Test computer
IAEA0929/01 NORSK DATA 560 DEC VAX 8810
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3. DESCRIPTION OF PROGRAM OR FUNCTION

The program solves the neutron  transport equation in X-Y geometry. Only isotropic scattering is permitted.
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4. METHOD OF SOLUTION

The integral form of the neutron transport equation is solved by the interface current method. The problem is broken into small regions. The transport equation is setup in each of these small regions. The outgoing neutron current at one surface  is related to the incoming currents at the other surfaces of the region and the neutron sources inside the region. The outgoing current of one region is the incoming current of adjacent regions. Associated Legendre polynomials are used to represent the angular dependence of fluxes. The weighted residual method is used to find the expansion coefficients of the angular fluxes. Making use of the  superposition principle of neutron currents, inner iterations are performed over the current components. Outer iterations are performed over groups. Numerical integrations are performed by Gauss quadrature. Neutron conservation is imposed for the calculation of transmission probabilities of current components and also in finding the average flux inside a region.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

No restrictions exist on the maximum number of energy groups or maximum number of meshes usable. The main storage array is presently 100K words, easily extendible due to variable dimensioning. However, due to the  fixed dimension of the built-in matrix inversion routine, the maximum number of angular expansion functions is limited to ten.
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6. TYPICAL RUNNING TIME

For a 500 flux point problem with flux convergence at any point lower than 1*10**(-3), and eigenvalue convergence lower than 1*10**(-5), CPU time is 15 minutes.
IAEA0929/01
The test case ran at NEADB on a DEC VAX 8810 computer in 3 minutes of CPU time.
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7. UNUSUAL FEATURES OF THE PROGRAM

Unlike the discrete ordinate method for solving the neutron transport equation (e.g. TWOTRAN), this code does not suffer from negative fluxes and ray effects. Use  of P2 half space expansion for angular flux is sufficient for most problems. Use of higher order expansions is yet to be studied which  is easily possible using the present code.
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8. RELATED AND AUXILIARY PROGRAMS:  There is no auxiliary program.
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9. STATUS
Package ID Status date Status
IAEA0929/01 14-FEB-1990 Tested at NEADB
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10. REFERENCES:
IAEA0929/01, included references:
- P. Mohanakrishnan :
  Choice of Angular Current Approximations for Solving Neutron
  Transport Problems in 2-D by Interface Current Approach.
  Reprint from "Annals of Nuclear Energy", Vol.9 (1982), pp. 261-274
- P. Mohanakrishnan :
  A Guide to the Use of Computer Code - RICANT.
  RG/RPD-311  (December 1987)
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11. MACHINE REQUIREMENTS:  Memory-100K words.
IAEA0929/01
To run the test case on a VAX 8810, about 400K bytes of main storage are required.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA0929/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  Standard.
IAEA0929/01
VMS V5.1 (VAX 8810).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:  None.
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15. NAME AND ESTABLISHMENT OF AUTHORS

         P. Mohanakrishnan
         Reactor Physics Division
         Third floor, GSB, IGCAR
         Kalpakkam, T.N., 603102, India
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16. MATERIAL AVAILABLE
IAEA0929/01
File name File description Records
IAEA0929_01.001 Ricant information file 127
IAEA0929_01.002 Ricant FORTRAN source file 1569
IAEA0929_01.003 Ricant sample problem input 33
IAEA0929_01.004 Ricant sample problem output 351
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17. CATEGORIES
  • C. Static Design Studies

Keywords: neutron transport equation, two-dimensional, x-y.