Abstract
The numerical solution of linear multi-energy-group neutron transport equation is required in several analyses in nuclear reactor physics and allied areas. Computer codes based on the discrete ordinates (Sn) method are commonly used for this purpose. These codes solve external source problem and K-eigenvalue problem. The overall solution technique involves solution of source problem in each energy group as intermediate procedures. Such a single-group source problem is solved by the so-called Source Iteration (SI) method. As is well-known, the SI-method converges very slowly for optically thick and highly scattering regions, leading to large CPU times. Over last three decades, many schemes have been tried to accelerate the SI; the most prominent being the Diffusion Synthetic Acceleration (DSA) scheme. The DSA scheme, however, often fails and is also rather difficult to implement. In view of this, in 1997, Ramone and others have developed a new acceleration scheme called Transport Synthetic Acceleration (TSA) which is much more robust and easy to implement. This scheme has been recently incorporated in 2-D and 3-D in-house codes at BARC. This report presents studies on the utility of TSA scheme for fairly general test problems involving many energy groups and anisotropic scattering. The scheme is found
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Modak, R S;
Kumar, Vinod;
Menon, S V.G.;
[1]
Gupta, Anurag
[2]
- Theoretical Physics Div., Bhabha Atomic Research Centre, Mumbai (India)
- Reactor Physics Design Div., Bhabha Atomic Research Centre, Mumbai (India)
Citation Formats
Modak, R S, Kumar, Vinod, Menon, S V.G., and Gupta, Anurag.
Transport synthetic acceleration scheme for multi-dimensional neutron transport problems.
India: N. p.,
2005.
Web.
Modak, R S, Kumar, Vinod, Menon, S V.G., & Gupta, Anurag.
Transport synthetic acceleration scheme for multi-dimensional neutron transport problems.
India.
Modak, R S, Kumar, Vinod, Menon, S V.G., and Gupta, Anurag.
2005.
"Transport synthetic acceleration scheme for multi-dimensional neutron transport problems."
India.
@misc{etde_20729327,
title = {Transport synthetic acceleration scheme for multi-dimensional neutron transport problems}
author = {Modak, R S, Kumar, Vinod, Menon, S V.G., and Gupta, Anurag}
abstractNote = {The numerical solution of linear multi-energy-group neutron transport equation is required in several analyses in nuclear reactor physics and allied areas. Computer codes based on the discrete ordinates (Sn) method are commonly used for this purpose. These codes solve external source problem and K-eigenvalue problem. The overall solution technique involves solution of source problem in each energy group as intermediate procedures. Such a single-group source problem is solved by the so-called Source Iteration (SI) method. As is well-known, the SI-method converges very slowly for optically thick and highly scattering regions, leading to large CPU times. Over last three decades, many schemes have been tried to accelerate the SI; the most prominent being the Diffusion Synthetic Acceleration (DSA) scheme. The DSA scheme, however, often fails and is also rather difficult to implement. In view of this, in 1997, Ramone and others have developed a new acceleration scheme called Transport Synthetic Acceleration (TSA) which is much more robust and easy to implement. This scheme has been recently incorporated in 2-D and 3-D in-house codes at BARC. This report presents studies on the utility of TSA scheme for fairly general test problems involving many energy groups and anisotropic scattering. The scheme is found to be useful for problems in Cartesian as well as Cylindrical geometry. (author)}
place = {India}
year = {2005}
month = {Sep}
}
title = {Transport synthetic acceleration scheme for multi-dimensional neutron transport problems}
author = {Modak, R S, Kumar, Vinod, Menon, S V.G., and Gupta, Anurag}
abstractNote = {The numerical solution of linear multi-energy-group neutron transport equation is required in several analyses in nuclear reactor physics and allied areas. Computer codes based on the discrete ordinates (Sn) method are commonly used for this purpose. These codes solve external source problem and K-eigenvalue problem. The overall solution technique involves solution of source problem in each energy group as intermediate procedures. Such a single-group source problem is solved by the so-called Source Iteration (SI) method. As is well-known, the SI-method converges very slowly for optically thick and highly scattering regions, leading to large CPU times. Over last three decades, many schemes have been tried to accelerate the SI; the most prominent being the Diffusion Synthetic Acceleration (DSA) scheme. The DSA scheme, however, often fails and is also rather difficult to implement. In view of this, in 1997, Ramone and others have developed a new acceleration scheme called Transport Synthetic Acceleration (TSA) which is much more robust and easy to implement. This scheme has been recently incorporated in 2-D and 3-D in-house codes at BARC. This report presents studies on the utility of TSA scheme for fairly general test problems involving many energy groups and anisotropic scattering. The scheme is found to be useful for problems in Cartesian as well as Cylindrical geometry. (author)}
place = {India}
year = {2005}
month = {Sep}
}