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NEA-0625 DINE.

DINE, Neutron Flux, Neutron Dose Rate in Multi-Region Slab Reactor Shield by Removal Diffusion

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1. NAME OR DESIGNATION OF PROGRAM:  DINE.
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2. COMPUTERS
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Program name Package id Status Status date
DINE NEA-0625/01 Report 10-FEB-1993

Machines used:

No specified machine
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3. DESCRIPTION OF PROBLEM OR FUNCTION

DINE is a multigroup removal diffusion program which calculates the neutron flux and dose rate distribution in a reactor shield with multiregion slab geometry due to a cylindrical reactor core. From the integral transport equation for linear anisotropic scattering a difference equation has been derived, in which the mesh distance is proportional to the mean free path. This method gives an improvement of the deep penetration  of diffusing neutrons.
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4. METHOD OF SOLUTION

The removal flux is calculated in the same lethargy group structure and at the same mesh points as used in the  multigroup diffusion calculation following. To calculate the re- moval flux, numerical integration of the first collision source equation is carried out over the reactor core.

The essence of the method for the treatment of the diffusion equa- tion is that on the integral diffusion equations for the flux and current, a difference operation with respect to the space coordin- ates is performed, due to which the series expansion of the scat- tering integral becomes much more convergent and can be approximated more easily.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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6. TYPICAL RUNNING TIME

About 5 minutes for a 250 cm. thick shield on the 48 K Philips Electrologica X8.
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7. UNUSUAL FEATURES OF THE PROGRAM

An efficient difference form of the diffusion equation is used.
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8. RELATED AND AUXILIARY PROGRAMS

DINE can use the output of TEDDI-M  - a two-dimensional diffusion code for core calculations, to de- termine the neutron source distribution in the core and the flux values at the core boundary.

RAGA - a Monte Carlo code which calculates the transport of cap- ture gamma rays, can use the reaction rates in the shield delivered  by DINE.
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9. STATUS
Package ID Status date Status
NEA-0625/01 10-FEB-1993 Report Only
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10. REFERENCES

- K.A. Verschuur:
Approximation of the Transport Equation with Difference Equations,    Proc. of International Conf. on the Physics Problems of Reactor
  Shielding, Harwell (Sept. 1967) AERE-R 5773, Vol. 1,
  Paper RS/1.1/6.
- K.A. Verschuur:
DINE - A One-Dimensional Neutron Shielding Program with Physically    Determined Space Mesh Distances and Linear Anisotropic Scattering
  RCN-153, Petten (June 1971).
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11. MACHINE REQUIREMENTS

The program uses the paper tape reader, line-printer, magnetic drum, and 1, 2 or 3 magnetic tape units.
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHOR

          K. A. Verschuur
          Reactor Centrum Nederland
          Petten
          The Netherlands.
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16. MATERIAL AVAILABLE
NEA-0625/01
report                                                              REPPT
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17. CATEGORIES
  • J. Gamma Heating and Shield Design

Keywords: anisotropic scattering, dose rates, multigroup, neutron diffusion equation, neutron flux, one-dimensional, reactor cores, removal-diffusion, shielding.