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중성자 수송경계조건의 확산근사에 대한 연구A Study on Diffusion Approximations to Neutron Transport Boundary Conditions

Other Titles
A Study on Diffusion Approximations to Neutron Transport Boundary Conditions
Authors
노태완
Issue Date
2018
Publisher
한국방사성폐기물학회
Keywords
중성자; 수송; 확산; 경계조건; 핵연료주기; Neutrons; Transport; Diffusion; Boundary conditions; Nuclear fuel cycle
Citation
방사성폐기물학회지, v.16, no.2, pp.203 - 209
Journal Title
방사성폐기물학회지
Volume
16
Number
2
Start Page
203
End Page
209
URI
https://scholarworks.bwise.kr/hongik/handle/2020.sw.hongik/4497
DOI
10.7733/jnfcwt.2018.16.2.203
ISSN
1738-1894
Abstract
To correctly predict the neutron behavior based on diffusion calculations, it is necessary to adopt well-specified boundary conditions using suitable diffusion approximations to transport boundary conditions. Boundary conditions such as the zero net-current, the Marshak, the Mark, the zero scalar flux, and the Albedo condition have been used extensively in diffusion theory to approximate the reflective and vacuum conditions in transport theory. In this paper, we derive and analyze these conditions to prove their mathematical validity and to understand their physical implications, as well as their relationships with one another. To show the validity of these diffusion boundary conditions, we solve a sample problem. The results show that solutions of the diffusion equation with these well-formulated boundary conditions are very close to the solution of the transport equation with transport boundary conditions.
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