Home Slab albedo for linearly and quadratically anisotropic scattering kernel with modified FN method
Article
Licensed
Unlicensed Requires Authentication

Slab albedo for linearly and quadratically anisotropic scattering kernel with modified FN method

  • R. G. Türeci and D. Türeci
Published/Copyright: October 20, 2017
Become an author with De Gruyter Brill
Submit Manuscript Author Information
Kerntechnik
From the journal Kerntechnik Volume 82 Issue 5

Abstract

One speed, time independent and homogeneous medium neutron transport equation is solved with the anisotropic scattering which includes both the linearly and the quadratically anisotropic scattering kernel. Having written Case's eigenfunctions and the orthogonality relations among of these eigenfunctions, slab albedo problem is investigated as numerically by using Modified FN method. Selected numerical results are pesented in tables.

Kurzfassung

Die Eingruppen-, zeitunabhängige Neutronentransportgleichung für linear und quadratisch anisotrope Streukerne wird gelöst. Mit Hilfe der Case-Eigenfunktionen und der Orthogonalitätsbeziehungen zwischen diesen Eigenfunktionen wurde das Albedoproblem mit Hilfe der modifizierten FN-Methode numerisch untersucht. Ausgewählte numerische Ergebnisse werden in Tabellenform dargestellt.

* Corresponding author: E-mail: ()

References

1 CaseK. M.; ZweifelP. F.: Linear Transport Theory. Massachusetts: Addition-Wesley (1967)Search in Google Scholar

2 MikaJ.: Neutron transport with anisotropic scattering. Nuclear Science and Engineering11 (1961) 41510.13182/NSE61-1Search in Google Scholar

3 SiewertC. E.; BenoistP.: The FN Method in Neutron-Transport Theory, Part I: Theory and Applications. Nuclear Science and Engineering69 (1979) 156–16010.13182/NSE79-1Search in Google Scholar

4 GrandjeanP.; SiewertC. E.: The FN method in neutron transport theory Part II: applications and numerical results. Nuclear Science and Engineering69 (1979) 16110.13182/NSE79-A20608Search in Google Scholar

5 Güleçyüz, M. Ç.; TezcanC.: The F-N method anisotropic scattering in neutron transport theory: The critical slab problem. J. Quant. Spectrosc. Rad. Transfer56 (1996) 30910.1016/0022-4073(96)00057-XSearch in Google Scholar

6 Kaşkaş, A.; TezcanC.: The F-N method for anisotropic scattering in neutron transport theory: The half-space problems. J. Quant. Spectrosc. Rad. Transfer55 (1996) 4110.1016/0022-4073(95)00143-3Search in Google Scholar

7 KavenokyA.: The CN Method of Solving the Transport Equation: Application to Plane Geometry. Nuclear Science and Engineering65 (1978) 20910.13182/NSE78-A27152Search in Google Scholar

8 KaşkaşA., Güleçyüz, M. Ç., TezcanC.: The slab albedo problem using singular eigenfunctions and the third form of the transport equation. Ann Nucl Energy. 23 (1996) 137110.1016/0306-4549(95)00118-2Search in Google Scholar

9 Güleçyüz, M. Ç.; KaşkaşA.; TezcanC.: Slab albedo problem for anisotropic scattering using singualr eigenfunction solution of the C-N equations. J. Quant. Spectrosc. Rad. Transfer61 (1999) 32910.1016/S0022-4073(97)00241-0Search in Google Scholar

10 TezcanC.; KaşkaşA.; Güleçyüz, M. Ç.: The H-N method for solving linear transport equation: Theory and applications. J. Quant. Spectrosc. Rad. Transfer78 (2003) 24310.1016/S0022-4073(02)00224-8Search in Google Scholar

11 TüreciR. G.; TüreciD.: Time dependent albedo problem for quadratic anisotropic scattering. Kerntechnik72 (2007) 5910.3139/124.100319Search in Google Scholar

12 TüreciR. G.: The albedo problem for pure-quadratic anisotropic scattering with Inönü scattering. Kerntechnik75 (2010) 292–29710.3139/124.110086Search in Google Scholar

13 Türeci, D.; TüreciR. G.; TeğmenA.; Güleçyüz, M. Ç.: Solving the constant source problem for the quadratic anisotropic scattering kernel using the modified F-N method. Kerntechnik77 (2012) 60Search in Google Scholar

14 TüreciR. G.; Gülecyüz, M. Ç.: The slab albedo and criticality problem for the quadratic scattering kernel with the H-N method. Kerntechnik73 (2008) 17110.3139/124.100564Search in Google Scholar

15 TüreciR. G.; TüreciD.: Half-Space Albedo Problem with Modified FN Method for Linear and Quadratic Anisotropic Scattering. Kerntechnik82 (2017) 23910.3139/124.110641Search in Google Scholar

16 CaseK. M.; HofmannF.; PlaczekG.: Introduction to the theory of neutron diffusion, vol. 1. Los Alamos, 1953Search in Google Scholar

Received: 2017-07-25
Published Online: 2017-10-20
Published in Print: 2017-10-26

© 2017, Carl Hanser Verlag, München

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Modelling Human Resource Requirements for the Nuclear Industry in Europe
  7. Some uncertainty results obtained by the statistical version of the KARATE code system related to core design and safety analysis
  8. The integrity of NSSS and containment during extended station blackout for Kuosheng BWR plant
  9. Experimental investigation of effect of spacer on two phase turbulent mixing rate in subchannels of pressure tube type BWR
  10. Thermal-hydraulic analysis of research reactor core with different LEU fuel types using RELAP5
  11. The application of knowledge management and TRIZ for solving the safe shutdown capability of fire alarms in nuclear power plants
  12. Dose assessment for emergency workers in early phase of Fukushima Daiichi nuclear power plant accident
  13. Anti-neutrino flux in a research reactor for non-proliferation application
  14. Friction coefficient and limiter load test analysis by flexibility coefficient model of Hold-Down Spring of nuclear reactor vessel internals
  15. Robust observer based control for axial offset in pressurized-water nuclear reactors based on the multipoint reactor model using Lyapunov approach
  16. Internal and external hazards inside the containment in case of an emergency situation
  17. Slab albedo for linearly and quadratically anisotropic scattering kernel with modified FN method
https://doi.org/10.3139/124.110663

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Modelling Human Resource Requirements for the Nuclear Industry in Europe
  7. Some uncertainty results obtained by the statistical version of the KARATE code system related to core design and safety analysis
  8. The integrity of NSSS and containment during extended station blackout for Kuosheng BWR plant
  9. Experimental investigation of effect of spacer on two phase turbulent mixing rate in subchannels of pressure tube type BWR
  10. Thermal-hydraulic analysis of research reactor core with different LEU fuel types using RELAP5
  11. The application of knowledge management and TRIZ for solving the safe shutdown capability of fire alarms in nuclear power plants
  12. Dose assessment for emergency workers in early phase of Fukushima Daiichi nuclear power plant accident
  13. Anti-neutrino flux in a research reactor for non-proliferation application
  14. Friction coefficient and limiter load test analysis by flexibility coefficient model of Hold-Down Spring of nuclear reactor vessel internals
  15. Robust observer based control for axial offset in pressurized-water nuclear reactors based on the multipoint reactor model using Lyapunov approach
  16. Internal and external hazards inside the containment in case of an emergency situation
  17. Slab albedo for linearly and quadratically anisotropic scattering kernel with modified FN method
Sign up now to receive a 20% welcome discount
Institutional Access
How does access work?
Have an idea on how to improve our website?
Please write us.
© 2025 De Gruyter Brill
Downloaded on 28.10.2025 from https://www.degruyterbrill.com/document/doi/10.3139/124.110663/html
Scroll to top button