Determination of the exposure build-up factor in a slab using the LTSN method
-
B. A. Rodriguez
Abstract
In this paper an exposure build-up factor formulation is reported by solving the photon transport equation in a heterogeneous slab by the LTSN method, assuming the Klein-Nishina scattering kernel as the scattering differential cross section as well as the multigroup model in the wavelength variable. Numerical simulations and comparisons with available results in the literature are presented for different compositions containing water, iron and lead.
Kurzfassung
In dieser Arbeit wird über die Berechnung des Dosisaufbaufaktors durch Lösung der Photonentransportgleichung in einer heterogenen Platte mit Hilfe der LTSN Methode berichtet, sowohl unter Annahme des Klein-Nishina Streukerns als differentieller Streuquerschnitt wie auch mit dem Multigruppenmodell in verschiedenen Wellenlängen. Es werden numerische Simulationen und Vergleiche mit in der Literatur verfügbaren Ergebnissen für verschiedene Zusammensetzungen von Wasser, Blei und Eisen vorgestellt.
References
1Barichello, L. B.; Vilhena, M. T.: The LTSN method: a new analytical approach to solve the neutron transport equation. Kerntechnik56 (5) (1991) 334Suche in Google Scholar
2Vilhena, M. T.; Barichello, L. B.; Zabadal, J.; Segatto, C. F.; Cardona, A. V.: General solution of one-dimensional approximations to the transport equation. Progress in Nuclear Energy33 (1998) 99Suche in Google Scholar
3Velho, H. F. C.; Vilhena, M. T.; Retamoso, M. R.; Pazos, R. P.: An Application of the LTSN Method on an Inverse Problem in Hydrological Optics. Progress in Nuclear Energy, Great Britain42 n 4 (2003) 457Suche in Google Scholar
4BatistelaC. H.; VilhenaM. T.; BorgesV.: Determination of the effective multiplication factor in a slab by the LTSN method. Annals of Nuclear Energy26 (1999) 76110.1016/S0306-4549(98)00096-6Suche in Google Scholar
5BatistelaC. H.; VilhenaM. T.; BorgesV.: Criticality by the LTSN Method. Journal of Nuclear Science and Technology34 (1997) 60310.1080/18811248.1997.9733714Suche in Google Scholar
6Orengo, G.; Vilhena, M. T.; Graça, C. O.; Caldeira, A. D.; Gonçalves, G. A.: Recent Advances in the LTSN Method for Criticality Calculations in Slab Geometry. Annals of Nuclear Energy31 (2004) 219510.1016/j.anucene.2004.05.010Suche in Google Scholar
7Vasques, R.; Segatto, C. F.; VilhenaM. T.: The LTSN solution for the neutron transport equation in spherical geometry. Proceedings of 18th International Conference on Transport Theory, Rio de Janeiro, 2003, 265Suche in Google Scholar
8Larsen, E. W.; Vasques, R.; VilhenaM. T.: Particle transport in the 1-D diffusive atomic mix limit. Mathematics and Computation, Supercomputing, reactor Physics and Nuclear and Biological Applications, France, 2005Suche in Google Scholar
9Brancher, J. D.; Vilhena, M. T.; Segatto, C. F.: The LTSN solution for radiative transfer problem without azimuthal symmetry with severe anisotropy. Journal of Quantitative Spectroscopy and Radiative Transfer62 (6) (1999) 74310.1016/S0022-4073(98)00122-8Suche in Google Scholar
10Vargas, R.; Vilhena, M. T.: A closed-form solution for one-dimensional radiative conductive problem by the decomposition and LTSN methods. Journal of Quantitative Spectroscopy and Radiative Transfer61 (1998) 30310.1016/S0022-4073(97)00225-2Suche in Google Scholar
11ZabadalJ. S.; VilhenaM. T.; BaricheloL. B.: An Analytical Solution for the Two-dimensional for Discrete Ordinate Problem in a Convex Domain. Progress in Nuclear Energy31 (3) (1997) 225Suche in Google Scholar
12ZabadalJ. S.; VilhenaM. T.; BaricheloL. B.: Solution of the Three-Dimensional One-Group Discrete Ordinates Problem by the LTSN Method. Annals of Nuclear Energy22 (1995) 13110.1016/0306-4549(94)P3962-HSuche in Google Scholar
13Vilhena, M. T.; Pazos, R. P.: Convergence of the LTSN method: approach of CO semi groups. Progress in Nuclear Energy34 (1) (1999) 7710.1016/S0149-1970(97)00112-1Suche in Google Scholar
14Vilhena, M. T.; Pazos, R. P.: Convergence in transport theory. Applied Numerical Mathematics30 (1999) 79Suche in Google Scholar
15FitzgeraldJ. J.; BrownellG. L.; MahoneyF. J.: Mathematical Theory of Radiation Dosimetry, Gordon and Breach, New York, USA, 1967Suche in Google Scholar
16HirayamaH.; ShinK.: Application of the EGS4 Monte Carlo Code to a Study of Multilayer Gamma-Ray Exposure Buildup Factors, Journal of Nuclear Science and Technology35 (1998) 81610.1080/18811248.1998.9733949Suche in Google Scholar
17Hauser, E. B.; Pazos, R. P.; Vilhena, M. T.: An error bound estimate and convergence of the Nodal-LTSN solution in a rectangle. Annals of Nuclear Energy32 (2005) 114610.1016/j.anucene.2005.02.007Suche in Google Scholar
© 2006, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- The multipurpose thermalhydraulic test facility TOPFLOW: an overview on experimental capabilities, instrumentation and results
- Uncertainty in cross-section calculations for reactions induced by neutrons with energy above 0.1 MeV
- Determination of the exposure build-up factor in a slab using the LTSN method
- Lumped parameters analysis of the IAEA research reactor benchmark problem
- Assessment of the look-up table using the tubular and bundle CHF data and modification of the bundle correction factor
- A finite element model for static strength analysis of CANDU fuel bundle
- Effect of packing fraction variations on the multiplication factor in pebble-bed nuclear reactors
- Design of a dry cask storage system for spent LWR fuels: radiation protection, subcriticality, and heat removal aspects
- Radiological and thermal characteristics of CASTOR RBMK-1500 and CONSTOR RBMK-1500 casks for spent nuclear fuel storage at Ignalina Nuclear Power Plant
- Analyses of severe accident scenarios in RBMK-1500
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- The multipurpose thermalhydraulic test facility TOPFLOW: an overview on experimental capabilities, instrumentation and results
- Uncertainty in cross-section calculations for reactions induced by neutrons with energy above 0.1 MeV
- Determination of the exposure build-up factor in a slab using the LTSN method
- Lumped parameters analysis of the IAEA research reactor benchmark problem
- Assessment of the look-up table using the tubular and bundle CHF data and modification of the bundle correction factor
- A finite element model for static strength analysis of CANDU fuel bundle
- Effect of packing fraction variations on the multiplication factor in pebble-bed nuclear reactors
- Design of a dry cask storage system for spent LWR fuels: radiation protection, subcriticality, and heat removal aspects
- Radiological and thermal characteristics of CASTOR RBMK-1500 and CONSTOR RBMK-1500 casks for spent nuclear fuel storage at Ignalina Nuclear Power Plant
- Analyses of severe accident scenarios in RBMK-1500
