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Information Journal Paper

Title

USING NODAL EXPANSION METHOD IN CALCULATION OF REACTOR CORE WITH SQUARE FUEL ASSEMBLIES

Pages

  46-52

Abstract

 A polynomial nodal method is developed to solve few-group neutron diffusion equations in cartesian geometry. In this article, the effective multiplication factor, group flux and power distribution based on the nodal polynomial expansion procedure is presented. In addition, by comparison of the results the superiority of NODAL EXPANSION METHOD on finite-difference and finite-element are fully demonstrated. The comparison of the results obtained by these method with those of the well-known benchmark problems have shown that they are in very good agreement.

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    APA: Copy

    ABD ELAHZADEH, M.Y., & BROUSHKI, M.. (2009). USING NODAL EXPANSION METHOD IN CALCULATION OF REACTOR CORE WITH SQUARE FUEL ASSEMBLIES. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, -(2 (48)), 46-52. SID. https://sid.ir/paper/97876/en

    Vancouver: Copy

    ABD ELAHZADEH M.Y., BROUSHKI M.. USING NODAL EXPANSION METHOD IN CALCULATION OF REACTOR CORE WITH SQUARE FUEL ASSEMBLIES. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY[Internet]. 2009;-(2 (48)):46-52. Available from: https://sid.ir/paper/97876/en

    IEEE: Copy

    M.Y. ABD ELAHZADEH, and M. BROUSHKI, “USING NODAL EXPANSION METHOD IN CALCULATION OF REACTOR CORE WITH SQUARE FUEL ASSEMBLIES,” JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, vol. -, no. 2 (48), pp. 46–52, 2009, [Online]. Available: https://sid.ir/paper/97876/en

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