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Solving the criticality problem with the reflected boundary condition for the triplet anisotropic scattering with the modified FN method

  • R. G. Türeci
Veröffentlicht/Copyright: 12. Dezember 2015
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Kerntechnik
Aus der Zeitschrift Kerntechnik Band 80 Heft 6

Abstract

One speed, time independent neutron transport equation in slab geometry can be solved with the triplet anisotropic scattering for the criticality problem with the reflected boundary condition. The value of the critical slab thickness is investigated numerically by using the Modified FN (HN) method. Case's eigenfunctions, normalization relation and orthogonality relations must be derived for this scattering in order to use the Modified FN method. Some selected values, which can be calculated from the criticality equation, can be tabulated. Also the term which comes from the Poincaré-Bertrand formula may be added to the orthogonality formula of the continuum eigenfunction.

Kurzfassung

Die Ein-Gruppen, zeitabhängige Neutronen-Transportgleichung in Stabgeometrie kann mit der anisotropen Triplett-Streuung für das Kritikalitätsproblem mit reflektierter Randbedingung gelöst werden. Der Wert der kritischen Stabdicke wurde numerisch untersucht mit Hilfe der modifizierten FN (HN) Methode. Case-Eigenfunktionen, Normalisierungsbeziehung und Orthogonalitätsrelationen müssen für diese Streuung abgeleitet werden, um die modifizierte FN (HN) Methode anwenden zu können. Einige aus der Kritikalitätsgleichung berechnete ausgewählte Werte können in tabellarischer Form dargestellt werden. Der aus der Poincaré-Bertrand Formel stammende Term kann zur Orthogonalitätsformel der Kontinuum-Eigenfunktion hinzugefügt werden.

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Received: 2015-07-30
Published Online: 2015-12-12
Published in Print: 2015-12-17

© 2015, Carl Hanser Verlag, München

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https://doi.org/10.3139/124.110563

Artikel in diesem Heft

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Considering the uncertainties in empirical correlations for vertical countercurrent flow limitation (CCFL) with TRACE
  7. 3RIP trip startup test simulation of TRACE/PARCS model for Lungmen ABWR under different power and flow conditions
  8. Development of a new analytic function expansion nodal code, HexDANM, for solving the neutron diffusion equation in hexagonal-Z geometry
  9. Laser cleaning of steam generator tubing based on acoustic emission technology
  10. Axial enrichment profile in advance nuclear energy power plant at supercritical-pressures
  11. Analysis of the small break loss of coolant accident in the VVER-1000/V446 reactor
  12. Thermal hydraulic analysis of reactivity accidents in MTR research reactors using RELAP5
  13. Depletion of Gadolinium burnable poison in a PWR assembly with high burnup fuel
  14. Nuclear model calculations on cyclotron production of 51Cr
  15. Radiotracer application for characterization of nuclear grade anion exchange resins Tulsion A-23 and Dowex SBR LC
  16. Solving the criticality problem with the reflected boundary condition for the triplet anisotropic scattering with the modified FN method
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