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The criticality calculations for one-speed neutrons in a reflected slab with anisotropic scattering using the modified UN method

Published/Copyright: May 18, 2013
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Kerntechnik
From the journal Kerntechnik Volume 77 Issue 6

Abstract

The reflected critical slab problem is studied using Chebyshev polynomials of second kind in one-speed neutron transport theory. The variation of the critical thickness of the medium is investigated both in the case of linearly anisotropic scattering and reflecting boundary conditions. The critical half-thicknesses of the slab are calculated for selected values of the reflection coefficient and the anisotropy parameter. Numerical results obtained for the critical half-thickness are identical with the ones obtained by the PN method and the ones available in literature.

Kurzfassung

In diesem Beitrag wird die eindimensionale Lösung der Neutronentransportgleichungen unter Verwendung von Chebyshev-Polynomen zweiter Ordnung für eine Platte und für eine Geschwindigkeitsklasse von Neutronen vorgestellt. Dabei wird die kritische Dicke des Mediums unter Berücksichtigung einer linearen anisotropen Streuung und reflektierender Randbedingungen betrachtet. Die so berechneten Werte für die kritischen Halbwertdicken sind identisch sowohl mit den in der Literatur verfügbaren Werten als auch mit den Ergebnissen aus der PN-Methode.

References

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Received: 2012-4-30
Published Online: 2013-05-18
Published in Print: 2012-12-01

© 2012, Carl Hanser Verlag, München

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  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Remarks on boiling water reactor stability analysis – part 2: stability monitoring
  7. Irradiation tests on PHWR type fuel elements in TRIGA research reactor of INR Pitesti
  8. Heat transfer study of a submerged reactor channel under boil-off condition
  9. Dynamic assessment for life extension of nuclear power plants (NPPs) using system dynamics (SD) method
  10. Effect of using FLiBe and FLiNaBe molten salts bearing plutonium fluorides on the neutronic performance of PACER
  11. Evaluations of the CCFL and critical flow models in TRACE for PWR LBLOCA analysis
  12. Development of program DETSIM to simulate detector's full energy peak efficiency
  13. The criticality calculations for one-speed neutrons in a reflected slab with anisotropic scattering using the modified UN method
  14. A detailed investigation of interactions within the shielding to HPGe detector response using MCNP code
  15. Cosmic ray angular distribution employing plastic scintillation detectors and flash-ADC/FPGA-based readout systems
https://doi.org/10.3139/124.110272

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Remarks on boiling water reactor stability analysis – part 2: stability monitoring
  7. Irradiation tests on PHWR type fuel elements in TRIGA research reactor of INR Pitesti
  8. Heat transfer study of a submerged reactor channel under boil-off condition
  9. Dynamic assessment for life extension of nuclear power plants (NPPs) using system dynamics (SD) method
  10. Effect of using FLiBe and FLiNaBe molten salts bearing plutonium fluorides on the neutronic performance of PACER
  11. Evaluations of the CCFL and critical flow models in TRACE for PWR LBLOCA analysis
  12. Development of program DETSIM to simulate detector's full energy peak efficiency
  13. The criticality calculations for one-speed neutrons in a reflected slab with anisotropic scattering using the modified UN method
  14. A detailed investigation of interactions within the shielding to HPGe detector response using MCNP code
  15. Cosmic ray angular distribution employing plastic scintillation detectors and flash-ADC/FPGA-based readout systems
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