A discrete ordinates operator for the diffuse transmission of a mixed neutron beam through a multilayered medium
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M. P. de Abreu
Abstract
In this article the transport model and inductive approach reported in a recent work have been extended, and a discrete ordinates operator for the diffuse transmission of a mixed neutron beam through a multilayered medium is derived. At first, a mathematical description of the mixed beam transport problem that we are concerned with is given. The resulting mathematical problem is, according to Chandrasekhar, decomposed into uncollided and diffuse problems. After treating the uncollided problem analytically, a discrete ordinates formulation of the diffuse problem is considered. A set of spatially discretised equations that are free from spatial truncation error is then introduced. Finally, a discrete ordinates operator that replaces the entire multilayered medium in diffuse neutron transmission computations is derived inductively. To the best of our knowledge, such an operator has never been reported previously in neutron transport literature. Numerical results for a four-layer medium are presented to illustrate the computational merit of a computer code based on our diffuse transmission operator.
Kurzfassung
In diesem Beitrag wird das Transportmodell und der induktive Ansatz einer vorangegangenen Arbeit erweitert. Ein diskrete Ordinaten Operator für die diffuse Transmission eines gemischten Neutronenstrahls durch ein mehrschichtiges Medium wird hergeleitet. Zunächst wird das hier behandelte Transportproblem gemischter Neutronenstrahlen mathematisch beschrieben. Das sich daraus ergebende mathematische Problem zerfällt nach Chandrasekhar in einen Anteil vor dem ersten Stoß des Neutrons und in einen diffusen Anteil. Nach der analytischen Behandlung des Anteils vor dem ersten Stoß, wird eine Formulierung des diffusen Anteils nach der Methode der diskreten Ordinaten betrachtet. Es wird eine Reihe von räumlich diskretisierten Gleichungen eingeführt, die unabhängig sind von räumlichen Abbruchfehlern. Schließlich wird ein diskrete Ordinaten Operator induktiv hergeleitet, der das gesamte mehrschichtiges Medium ersetzt. Nach unserem Wissen wurde über einen solchen Operator in der Neutronentransportliteratur bisher nichts berichtet. Numerische Ergebnisse für ein 4-Schichten Medium werden vorgestellt, um die Vorteile eines Rechencodes auf der Basis unseres Operators für die diffuse Transmission zu erläutern.
References
1 Blizard, E. P.; Abbott, L. S.: Reactor Handbook, Vol. 3, Part B: Shielding. 2nd Ed., Interscience Publishers, New York (1962)Suche in Google Scholar
2 El-Sayed Abdo, A.; Megahid, R. M.: Homogeneous and multilayered shields for neutrons and gamma-rays. Jpn. J. Appl. Phys.40 (2001) 246010.1143/JJAP.40.2460Suche in Google Scholar
3 Laye, F.: Calculation of neutron fluxes and radioactivities in the biological shield of the Bugey 1 graphite-gas reactor. Proceedings of the 11th International Conference on Radiation Shielding (CD-ROM), Mountain Creek Conference Center, Pine Mountain, Georgia, USA, April 13–18, 2008, American Nuclear Society, La Grange Park, IL (2008)Suche in Google Scholar
4 Williams, J. G.; Insoo, J.; Sallee, W. W.; Cherng, M.: Benchmark experiments for space reactor neutron shielding of mission electronics. IEEE Trans. Nucl. Sci.51 (2004) 3658Suche in Google Scholar
5 Kang, H.-Y.; Park, C.-J.; Seo, K.-S.; Yoon, J.-S.: Evaluation of neutron shielding effects on various materials using a Cf-252 source. J. Kor. Phys. Soc.52 (2008) 1744Suche in Google Scholar
6 Rushton, R.; Schettler, D.: Neutron shielding design for well-logging shipping transport casks. Proceedings of the 11th International Conference on Radiation Shielding (CD-ROM), Mountain Creek Conference Center, Pine Mountain, Georgia, USA, April 13–18, 2008, American Nuclear Society, La Grange Park, IL (2008)Suche in Google Scholar
7 Wagner, F. M.; Loeper-Kabasakal, B.; Breitkreutz, H.; Petry, W.: Use of fission radiation in life sciences and materials characterisation. Transactions of the 13th International Topical Meeting on Research Reactor Fuel Management (CD-ROM), Vienna International Centre, Vienna, Austria, March 22–25, 2009, European Nuclear Society, Brussels, Belgium (2009)Suche in Google Scholar
8 Burgett, E.; Hertel, N.: Collimated thermal neutron beam line at Georgia Tech Graphite Pile Facility. Proceedings of the 15th Topical Meeting of the Radiation Protection & Shielding Division of ANS (CD-ROM), Mountain Creek Conference Center, Pine Mountain, Georgia, USA, April 13–18, 2008, American Nuclear Society, La Grange Park, IL (2008)Suche in Google Scholar
9 Auterinen, I.; Kankaantanta, L.: Reactor-based BNCT facilities: current status and future prospects. Proceedings of the 13th International Congress on Neutron Capture Therapy (CD-ROM), Palazzo dei Congressi, Villa Vittoria, Florence, Italy, November 2–7, 2008, International Society for Neutron Capture Therapy, Pavia, Italy (2008)Suche in Google Scholar
10 Ingersoll, D. T.; Slater, C. O.; Williams, L. R.: BNCT filter design studies for the ORNL tower shielding facility. Trans. Am. Nucl. Soc.75 (1996) 28Suche in Google Scholar
11 Nigg, D. W.; Sloan, P. E.; Venhuizen, J. R.; Wemple, C. A.; Tripard, G. E.; Fox, K.; Corwin, E.: Initial performance characterization for a thermalized neutron beam for neutron capture research at Washington State University. Trans. Am. Nucl. Soc.92 (2005) 807Suche in Google Scholar
12 Terlizzi, R.; Colonna, N.; Colangelo, P.; Marrone, S.; Tagliente, G.; Maiorana, A.; Rainò, A.; Variale, V.: Design of an accelerator-based neutron source for neutron capture therapy. Proceedings of the 13th International Congress on Neutron Capture Therapy (CD-ROM), Palazzo dei Congressi, Villa Vittoria, Florence, Italy, November 2–7, 2008, International Society for Neutron Capture Therapy, Pavia, Italy (2008)10.1016/j.apradiso.2009.03.116Suche in Google Scholar PubMed
13 Zimin, S.; Allen, B. J.: Study of moderator thickness for an accelerator-based neutron irradiation facility for boron neutron capture therapy using the 7Li (p, n) 7Be reaction near threshold. Phys. Med. Biol.45 (2000) 5910.1088/0031-9155/45/1/305Suche in Google Scholar PubMed
14 de Abreu, M. P.: On the development of computational tools for the design of beam assemblies for boron neutron capture therapy. J. Computer-Aided Mater. Des.14 (2007) 23510.1007/s10820-006-9041-xSuche in Google Scholar
15 de Abreu, M. P.: Mixed singular-regular boundary conditions in multislab radiation transport. J. Comp. Phys.197 (2004) 167Suche in Google Scholar
16 Chandrasekhar, S.: Radiative Transfer. Dover Publications, New York (1960)Suche in Google Scholar
17 Lewis, E. E.; MillerJr., W. F.: Computational Methods of Neutron Transport. American Nuclear Society, La Grange Park, IL (1993)Suche in Google Scholar
18 Youse, B. K.: Mathematical Induction, Prentice-Hall, Englewood Cliffs, NJ (1964)Suche in Google Scholar
19 Press, W. H.; Teukolsky, S. A.; Vetterling, W. T.; Flannery, B. P.: Numerical Recipes in FORTRAN 77: The Art of Scientific Computing. 2nd Ed., Cambridge University Press, New York (1996)Suche in Google Scholar
© 2010, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Adaptation of the FEMAXI-6 code and RBMK fuel rods model testing employing the best estimate approach
- In-reactor measurements of fuel centerline temperature variation during power change
- Pertinence of tests used for conformity assessments of fire resistance of nuclear power plant components – opinion of several institutions in Europe
- Analysis of the instability of OTSG of movable nuclear power devices by using the multivariable frequency domain method
- Steady state thermal hydraulic calculations for MTR plate-type research reactors
- Production cross sections of medical 110,111In radionuclides
- Nuclear level density parameters of some largely deformed nuclei of medical radionuclides in low-lying collective excitation modes
- A discrete ordinates operator for the diffuse transmission of a mixed neutron beam through a multilayered medium
- Kritikalitätssicherheit der Endlagerung ausgedienter Kernbrennstoffe
- Technical Notes/Technische Mitteilungen
- Methods for thin foil thickness determination by using alpha spectroscopy
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Adaptation of the FEMAXI-6 code and RBMK fuel rods model testing employing the best estimate approach
- In-reactor measurements of fuel centerline temperature variation during power change
- Pertinence of tests used for conformity assessments of fire resistance of nuclear power plant components – opinion of several institutions in Europe
- Analysis of the instability of OTSG of movable nuclear power devices by using the multivariable frequency domain method
- Steady state thermal hydraulic calculations for MTR plate-type research reactors
- Production cross sections of medical 110,111In radionuclides
- Nuclear level density parameters of some largely deformed nuclei of medical radionuclides in low-lying collective excitation modes
- A discrete ordinates operator for the diffuse transmission of a mixed neutron beam through a multilayered medium
- Kritikalitätssicherheit der Endlagerung ausgedienter Kernbrennstoffe
- Technical Notes/Technische Mitteilungen
- Methods for thin foil thickness determination by using alpha spectroscopy