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Reconstruction of the Shape of Unknown Obstacles in Freshwater
ZHUANG Hong-wei, MA Yi-chen, ZHANG Zhi-bin, WANG Jian
CHINESE JOURNAL OF COMPUTATIONAL PHYSICS 2004, 21 (
1
): 54-60.
Abstract
(
221
)
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(210KB)(
1121
)
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The inverse scattering problem is converted to an operator equation
F
(
Γ
)=
f
, which consists of the far field operator
F
, the measured far field data
f
and the shape
Γ
of the unknown obstacle. Using the Levenberg-Marquardt method and the derivative of
F
on
Γ
, in-troduced by A. Kirsh, this equation is solved and the shape
Γ
is determined. The numerical results show that this algorithm is practical and efficient.
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MIXED AND DISCONTINUOUS FINITE ELEMENT METHOD USED TO NEUTRON DIFFUSION EQUATION
YANG Yin-ling, GUO Xiu-lan, MA Yi-chen, ZHANG Zhi-bin
CHINESE JOURNAL OF COMPUTATIONAL PHYSICS 2001, 18 (
6
): 563-568.
Abstract
(
190
)
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(169KB)(
996
)
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A variational formula combining mixed finite element method with discontinuous finite element method is derived for solving the two group neutron diffusion equation in 2D. According to the variational formula, a numerical test is given whose result proves that the variational formula is reasonable and practicable. In order to improve the precision of the calculation, there are more to be studied.
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EXISTENCE,UNIQUENESS AND STABILITY OF INVERSE NEUMANN BOUNDARY VALUE PROBLEM OF POISSON EQUATION
CHEN Qi, MA Yi-chen, YING Gen-jun, YANG Xiao-bin
CHINESE JOURNAL OF COMPUTATIONAL PHYSICS 2001, 18 (
6
): 531-538.
Abstract
(
641
)
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(285KB)(
1103
)
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Results of existence,uniqueness and stability recovering the domain from a measured data of Poisson equation are obtained.The results of determining the shape of unknown domain are proven with Sobolev theory and the fundamental solution of Poisson equation.
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CALCULATION OF NEUTRON COLLISION PROBABILITIES ON THE MIXED REGION IN TWO-DIMENSION
Ma yi-chen, Gao Wei Fan, Bi-jian, Tang Fu-chu, Yao En-de
CHINESE JOURNAL OF COMPUTATIONAL PHYSICS 1987, 4 (
3
): 263-274.
Abstract
(
258
)
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918
)
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In this paper the formulae of the collision probobilities for the isotro-pic two-dimensional neutron transport problem on the mixed region consisting of rectangular or triangle cells are given. Based on these formulae the code has been developed and applied to tow-dimensional mixed cells calculations. The calculated results show good agreement with those of Montecalo method and conservation principles.
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