2017
DOI: 10.17146/tdm.2017.19.3.3668
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Analysis of Reactivity Coefficient Change Due to Burn Up in Ap1000 Reactor Core Using Nodal3

Abstract: ANALYSIS OF REACTIVITY COEFFICIENT CHANGE DUE TO BURN UP IN AP1000REACTOR CORE USING NODAL3. One of the important things in reactor safety is the value of inherent safety parameter namely reactivity coefficient. These inherent safety parameters are fuel and moderator temperature coefficients of reactivity. The objective of the study is to obtain the change of those reactivity coefficients as a function of fuel burn up during the cycle operation of AP 1000 reactor core. Fuel and moderator temperature coefficien… Show more

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Cited by 3 publications
(2 citation statements)
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“…One of them is the evaluation and analysis of reactor core of nuclear power plant. Some analysis on PWR core have been done, either for static parameter [1][2][3][4] and dynamic parameter [5][6][7]. In addition, research on transient analysis on PWR core has been conducted [8,9].…”
Section: Introductionmentioning
confidence: 99%
“…One of them is the evaluation and analysis of reactor core of nuclear power plant. Some analysis on PWR core have been done, either for static parameter [1][2][3][4] and dynamic parameter [5][6][7]. In addition, research on transient analysis on PWR core has been conducted [8,9].…”
Section: Introductionmentioning
confidence: 99%
“…In this work, a coupled N/TH code based on threedimensional neutron diffusion theory, MTR-DYN code, is used for the present optimization and safety analyses. This code has previously also been used for transient analysis of the RSG-GAS reactor [17,18].…”
mentioning
confidence: 99%