The Boundary Source Method with Arbitrary Order Anisotropic Scattering

Research output: Contribution to journalArticlepeer-review

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The Boundary Source Method with Arbitrary Order Anisotropic Scattering. / Van den Eynde, Gert; Beauwens, Robert; Mund, Ernest; Aït Abderrahim, Hamid (Peer reviewer).

In: Nuclear Science and Engineering, Vol. 155, No. 2, 01.02.2007, p. 300-309.

Research output: Contribution to journalArticlepeer-review

Harvard

Van den Eynde, G, Beauwens, R, Mund, E & Aït Abderrahim, H 2007, 'The Boundary Source Method with Arbitrary Order Anisotropic Scattering', Nuclear Science and Engineering, vol. 155, no. 2, pp. 300-309.

APA

Van den Eynde, G., Beauwens, R., Mund, E., & Aït Abderrahim, H. (2007). The Boundary Source Method with Arbitrary Order Anisotropic Scattering. Nuclear Science and Engineering, 155(2), 300-309.

Vancouver

Van den Eynde G, Beauwens R, Mund E, Aït Abderrahim H. The Boundary Source Method with Arbitrary Order Anisotropic Scattering. Nuclear Science and Engineering. 2007 Feb 1;155(2):300-309.

Author

Van den Eynde, Gert ; Beauwens, Robert ; Mund, Ernest ; Aït Abderrahim, Hamid. / The Boundary Source Method with Arbitrary Order Anisotropic Scattering. In: Nuclear Science and Engineering. 2007 ; Vol. 155, No. 2. pp. 300-309.

Bibtex - Download

@article{56066967f034436eb48675d05bce9cf7,
title = "The Boundary Source Method with Arbitrary Order Anisotropic Scattering",
abstract = "The boundary source method is an integral method introduced in the late 1960s for solving one-dimensional one-velocity transport problems arising in cell calculations. This method was further developed in various ways since that period and found to be of particular interest for recent applications to nodal transport codes. We have developed a boundary source code in plane geometry that allows for anisotropic scattering of arbitrary high order, and it is the purpose of this paper to display the extreme accuracy of this code, showing hereby that the boundary source method is probably the most accurate transport solution method available today for solving piecewise homogeneous transport problems.",
keywords = "neutron transport, anisotropic scattering, boundary source method",
author = "{Van den Eynde}, Gert and Robert Beauwens and Ernest Mund and {A{\"i}t Abderrahim}, Hamid",
note = "Score = 10",
year = "2007",
month = feb,
day = "1",
language = "English",
volume = "155",
pages = "300--309",
journal = "Nuclear Science and Engineering",
issn = "0029-5639",
publisher = "Taylor & Francis (CRC)",
number = "2",

}

RIS - Download

TY - JOUR

T1 - The Boundary Source Method with Arbitrary Order Anisotropic Scattering

AU - Van den Eynde, Gert

AU - Beauwens, Robert

AU - Mund, Ernest

A2 - Aït Abderrahim, Hamid

N1 - Score = 10

PY - 2007/2/1

Y1 - 2007/2/1

N2 - The boundary source method is an integral method introduced in the late 1960s for solving one-dimensional one-velocity transport problems arising in cell calculations. This method was further developed in various ways since that period and found to be of particular interest for recent applications to nodal transport codes. We have developed a boundary source code in plane geometry that allows for anisotropic scattering of arbitrary high order, and it is the purpose of this paper to display the extreme accuracy of this code, showing hereby that the boundary source method is probably the most accurate transport solution method available today for solving piecewise homogeneous transport problems.

AB - The boundary source method is an integral method introduced in the late 1960s for solving one-dimensional one-velocity transport problems arising in cell calculations. This method was further developed in various ways since that period and found to be of particular interest for recent applications to nodal transport codes. We have developed a boundary source code in plane geometry that allows for anisotropic scattering of arbitrary high order, and it is the purpose of this paper to display the extreme accuracy of this code, showing hereby that the boundary source method is probably the most accurate transport solution method available today for solving piecewise homogeneous transport problems.

KW - neutron transport

KW - anisotropic scattering

KW - boundary source method

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_76608

UR - http://knowledgecentre.sckcen.be/so2/bibref/4032

M3 - Article

VL - 155

SP - 300

EP - 309

JO - Nuclear Science and Engineering

JF - Nuclear Science and Engineering

SN - 0029-5639

IS - 2

ER -

ID: 306579