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- W2016988652 abstract "A theoretical concept for the description of 3D nuclear kinetics, heat conduction and the thermal-hydraulic single and two-phase flow phenomena in a 3D light water reactor core simulated by parallel channels is presented. The heat generation within each fuel element is described by a 3D core kinetics code employing a two-group diffusion theory model. Finite differences are used to approximate the diffusion equations for fast and thermal neutron fluxes. The resulting algebraic equations are solved by an iterative procedure. The heat transport out of a fuel element is determined from a finite difference version of the Fourier heat conduction equation applied in the radial direction only. An implicit solution for the temperature in each radial cell is found using a tri-diagonal algorithm. The heat transfer rate into the coolant channel is calculated from the clad and coolant temperatures. The thermal-hydraulic part of the code is based on the generally applicable and self-contained ‘coolant channel module’ (CCM) developed by Hoeld [Hoeld, A., 2004a, A theoretical concept for a thermal-hydraulic 3D parallel channel core model. PHYSOR 2004, April 25–29, Chicago, USA; Hoeld, A., 2004b, Are separate-phase thermal-hydraulic models better than mixture-fluid approaches. It depends. Rather not. International Conference on ‘Nuclear Engineering for New Europe 2004’. September 6–9, Portoroz, Slov; Hoeld, A., 2005, A thermal-hydraulic drift-flux based mixture-fluid model for the description of single- and two-phase flow along a general coolant channel. NURETH-11, October 2–6, Avignon, France], which offers a new approach for the simulation of steady state and transient behaviour of single- or two-phase flow within a general coolant channel. The concept is demonstrated in the experimental code X3D, concentrating in a first stage on the steady state behaviour of a hypothetical BWR or PWR core which consists of a central channel and four quadrants. Initial results are presented to demonstrate the viability of the proposed concept. This code therefore tests a different theoretical approach of how to determine the essential 3D thermal-hydraulic mass flow distribution into parallel channels by maintaining equal pressure decrease terms over all channels." @default.
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- W2016988652 date "2006-08-01" @default.
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- W2016988652 title "Initial version of an integrated thermal hydraulics and neutron kinetics 3D code X3D" @default.
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- W2016988652 doi "https://doi.org/10.1016/j.nucengdes.2006.04.016" @default.
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