An improved response matrix method and its verification by one-dimensional analysis on fast reactors.
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概要
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The current response matrix method based on isotropic (P<SUB>0</SUB>) neutron angular distri-bution has been improved by effectively including a linearly anisotropic (P<SUB>1</SUB>) angular distribution. The proposed method does not take into account the P<SUB>1</SUB> component directly, but it includes the effect of this component through consideration of the relation between the P<SUB>0</SUB> and P<SUB>1</SUB> components. The accuracy of the proposed method has been verified by comparing with exact calculation the diffusion length obtained by the present method in a uniform and infinite system: The diffusion length can be evaluated within 1% error. The present method has been further applied to one-dimensional fast reactor systems: The power distribution can be evaluated within 1%, and the neutron multiplication factor within 0.1%ΔK/K, in reference to S<SUB>16</SUB>, calculations. This accuracy is comparable to that of a response matrix method in which the Legendre expansion about the angle is per-formed with components taken up to P<SUB>1</SUB>. The proposed method adopts the same number of unknown components of neutron current as in the current response matrix method (order P<SUB>0</SUB>). The computing time is thus of comparable order between these two methods, which is much shorter than for the response matrix method using the P<SUB>1</SUB> angular distri-bution. The proposed method can hence be considered useful for one-dimensional transport problems, and should also have good prospects of proving equally effective for multi-dimensional problems.
- 一般社団法人 日本原子力学会の論文
著者
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TAKEDA Toshikazu
Atomic Energy Research Laboratory, Hitachi Ltd.
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AZEKURA Kazuo
Atomic Energy Research Laboratory, Hitachi Ltd.
関連論文
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- An improved response matrix method and its verification by one-dimensional analysis on fast reactors.
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