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http://dx.doi.org/10.1016/j.net.2019.07.024

Reactor core analysis through the SP3-ACMFD approach Part II: Transient solution  

Mirzaee, Morteza Khosravi (Faculty of Engineering, Shahid Beheshti University)
Zolfaghari, A. (Faculty of Engineering, Shahid Beheshti University)
Minuchehr, A. (Faculty of Engineering, Shahid Beheshti University)
Publication Information
Nuclear Engineering and Technology / v.52, no.2, 2020 , pp. 230-237 More about this Journal
Abstract
In this part, an implicit time dependent solution is presented for the Boltzmann transport equation discretized by the analytic coarse mesh finite difference method (ACMFD) over the spatial domain as well as the simplified P3 (SP3) for the angular variable. In the first part of this work we proposed a SP3-ACMFD approach to solve the static eigenvalue equations which provide the initial conditions for temp dependent equations. Having solved the 3D multi-group SP3-ACMFD static equations, an implicit approach is resorted to ensure stability of time steps. An exponential behavior is assumed in transverse integrated equations to establish a relationship between flux moments and currents. Also, analytic integration is benefited for the time-dependent solution of precursor concentration equations. Finally, a multi-channel one-phase thermal hydraulic model is coupled to the proposed methodology. Transient equations are then solved at each step using the GMRES technique. To show the sufficiency of proposed transient SP3-ACMFD approximation for a full core analysis, a comparison is made using transport peers as the reference. To further demonstrate superiority, results are compared with a 3D multi-group transient diffusion solver developed as a byproduct of this work. Outcomes confirm that the idea can be considered as an economic interim approach which is superior to the diffusion approximation, and comparable with transport in results.
Keywords
Multi-dimensional multi-group neutron transport; Reactor core analysis; Simplified $P_3$ ($SP_3$) equations; ACMFD method; Static and transient analysis; PARCS code; Thermal feedbacks;
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