KMID : 0371820000320060605
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Nuclear Engineering and Technology 2000 Volume.32 No. 6 p.605 ~ p.617
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Development of the Discrete-Ordinates, Nodal Transport Methods Using the Simplified Even-Parity Neutron Transport Equation
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Noh, Taewan
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Abstract
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neutron;transport;diffusion;nodal;discrete-ordinates;even-parity;simplified even-parity;scalar flux;angular flux
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KEYWORD
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