Application of the spectral Green's function method for numerically solving discrete ordinates problems in cylindrical geometry
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H. Öztürk
Abstract
The spectral Green's function (SGF) method is used to solve numerically the transport of neutrons in an infinite homogeneous cylindrical domain. In the method, the scattering of neutrons is assumed to be isotropic and the transport equation in cylindrical geometry is reduced to plane-like transport equation by using our reasonable approach. Then, the plane-like transport equation is solved by using the SGF method and the results are compared with those already obtained by the Diamond Difference (DD) scheme to check the accuracy of the results. The agreement of the results is good and it can be concluded that the SGF method is very effective for the numerical solution of the transport equation.
Kurzfassung
Die Methode der spektralen Greenfunktion (SGF) wird angewendet zur numerischen Lösung der Transportgleichung für Neutronen in einem infiniten homogenen zylindrischen Gebiet. Bei dieser Methode wird die Streuung von Neutronen als isotrop angenommen. Die Transportgleichung in Zylindergeometrie wird mit Hilfe des hier vorgeschlagenen Ansatzes reduziert auf eine ebene Transportgleichung. Diese wird dann mit Hilfe der SGF Methode gelöst. Zur Überprüfung der Genauigkeit werden die Ergebnisse verglichen mit den Ergebnissen, die mit dem „Diamond Difference (DD)“ Modell erhalten wurden. Die Übereinstimmung der Ergebnisse ist gut. Daraus ergibt sich, dass die SGF Methode ein sehr effektives Verfahren zur Lösung der Transportgleichung ist.
References
1 Carlson, B. G.; Lathrop, K. D.: Transport theory – The method of discrete ordinates. In: Greenspan, H.; Kelber, C. N.; Okrent, D.: editors. Computing methods in reactor physics. New York, Gordon and Breach, 1968Suche in Google Scholar
2 Pomraning, G. C.: The transport equation in general geometry. Nucl. Sci. Eng.101 (1989) 330Suche in Google Scholar
3 Mitsis, G. J.: Transport solutions to the monoenergetic critical problems. Ph.D. Thesis, (1963), Argonne National Laboratory, ANL-6787 10.2172/4118021Suche in Google Scholar
4 Fletcher, J. K.: The solution of the multigroup neutron transport equation using spherical harmonics. Nucl. Sci. Eng.34 (1983) 33Suche in Google Scholar
5 Wu, Y.; Xie, Z.; Fischer, U.: A discrete ordinates nodal method for one-dimensional neutron transport calculation in curvilinear geometries. Nucl. Sci. Eng.133 (1999) 350Suche in Google Scholar
6 Asadzadeh, M.: A finite element method for the neutron transport equation in an infinite cylindrical domain. SIAM J. Numer. Anal.35 (1998) 1299Suche in Google Scholar
7 Siewert, C. E.; Thomas, J. R.Jr.: Neutron transport calculations in cylindrical geometry. Nucl. Sci. Eng.87 (1984) 107Suche in Google Scholar
8 Khouaja, H.; Edwards, D. R.; Tsoulfanidis, N.: Spherical harmonics-finite element treatment of neutron transport in cylindrical geometry. Ann. Nucl. Energy24 (1997) 515Suche in Google Scholar
9 Lee, C. E.; Fan, W. C. P.; Dias, M. P.: Analytical solution to the moment transport equations-II. Ann. Nucl. Energy12 (1985) 61310.1016/0306-4549(85)90013-1Suche in Google Scholar
10 Wood, J.: A multigroup finite-element solution of the neutron transport equation-II, r-z geometry. Ann. Nucl. Energy12 (1985) 217Suche in Google Scholar
11 Bell, G. I.; Glasstone, S.: Nuclear reactor theory. New York, VNR Company1972Suche in Google Scholar
12 Barros, R.C.; Larsen, E. W.: A numerical method for one-group slab geometry discrete ordinates problems with no spatial truncation error. Nucl. Sci. Eng.104 (1990) 199Suche in Google Scholar
13 Larsen, E. W.: The asymptotic diffusion limit of discretized transport problems. Nucl. Sci. Eng.112 (1992) 336Suche in Google Scholar
14 Yavuz, M.: A one-d simplified discrete-ordinates method with no spatial truncation error. Ann. Nucl. Energy22 (1995) 203Suche in Google Scholar
15 Anlı, F.: Spectral Green's function method for neutron transport: Isotropic, forward, and backward scattering in 1-D slab geometry. Ann. Nucl. Energy28 (2001) 1033Suche in Google Scholar
16 Abreu, M.; Filho, H. A.; Barros, R. C.: A numerical method for multigroup slab-geometry eigenvalue problems in transport theory with no spatial truncation error. Transp. Theory Stat. Phys.25 (1996) 61Suche in Google Scholar
17 Lewis, E. E.; Miller, W. F.Jr.: Computational Methods of Neutron Transport Theory. Illinois, American Nuclear Society, 1993Suche in Google Scholar
18 Yasa, F.; Anlı, F.: An analytic and numerical solution with spectral Green's function method for transport equation in spherical geometry. J. Quant. Spectrosc. Radiat. Transfer90 (2005) 115Suche in Google Scholar
19 Morel, J. E.; Lathrop, K. D.: Singular solutions, integral transport theory, and the Sn method. Nucl. Sci. Eng.147 (2004) 158Suche in Google Scholar
© 2008, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Application of the HN method to radiative heat transfer for a non-conservative slab
- Application of the spectral Green's function method for numerically solving discrete ordinates problems in cylindrical geometry
- Chebyshev polynomial (TN) approximation to neutron transport theory and application to the critical slab problem
- Spherical albedo problem for isotropic scattering
- The slab albedo and criticality problem for the quadratic scattering kernel with the HN method
- An analytical solution for the time-dependent SN transport equation in a slab
- Deterministic calculation of grey Dancoff factors in cluster cells with cylindrical outer boundaries
- New calculations of excitation functions of some positron emitting and single photon emitting radioisotopes
- Prediction of the time-dependent failure rate for normally operating components taking into account the operational history
- Assessment of FEMAXI and TESPA-ROD codes for modelling of BDBA in RBMK-1500
- A study on the neutronic performance of the ARIES-RS fusion reactor with various coolants bearing nuclear fuel
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Application of the HN method to radiative heat transfer for a non-conservative slab
- Application of the spectral Green's function method for numerically solving discrete ordinates problems in cylindrical geometry
- Chebyshev polynomial (TN) approximation to neutron transport theory and application to the critical slab problem
- Spherical albedo problem for isotropic scattering
- The slab albedo and criticality problem for the quadratic scattering kernel with the HN method
- An analytical solution for the time-dependent SN transport equation in a slab
- Deterministic calculation of grey Dancoff factors in cluster cells with cylindrical outer boundaries
- New calculations of excitation functions of some positron emitting and single photon emitting radioisotopes
- Prediction of the time-dependent failure rate for normally operating components taking into account the operational history
- Assessment of FEMAXI and TESPA-ROD codes for modelling of BDBA in RBMK-1500
- A study on the neutronic performance of the ARIES-RS fusion reactor with various coolants bearing nuclear fuel