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1. Test ID: AER-DYN-003
Solution ID: DYN03s2
2. a, Solution Submitted by: Jan Hdek, Nuclear Research Institute Xe~ plc,
250 68 Xe~ , Czech Republic
Date: 2. 2. 2000
b, Reviewed by:
Date:
c, Accepted by:
3. Code or Program Applied:
DYN3D
4. Short Description of Code:
The code DYN3D was developed at FZ Rossendorf and it is used for investigations of reactivity transients in cores of thermal power reactors with hexagonal fuel elements. The 3-dimensional neutron kinetics model HEXDYN3D of the code is based on nodal expansion method for solving the two-group neutron diffusion equation. If we suppose that the reactor core is consisted from hexagonal fuel assemblies divided into a number of slices, than the nodes are the parts of the fuel assemblies in each slice. The neutron group constants are assumed to be spatially constant in each node. The solving of the time dependent neutron diffusion equations including the equations for delayed neutrons for all nodes is used for transient processes calculation. The thermo-hydraulic part FLOCAL consists of a two-phase flow model describing coolant behaviour and a fuel rod model. The fuel elements are simulated by separate coolant channels. Additional, some hot channels with power peaking factors belonging to chosen fuel elements can be considered. Several safety parameters as temperatures, DNBR and fuel enthalpy are evaluated. Macroscopic cross sections depending on thermo-hydraulic parameters and boron concentration are input data of the code. The stationary state and transient behaviour can be analyzed. The transient processes in the core can be investigated as long as the core geometry is maintained. For analyzing a static state, there are several possibilities to make the reactor critical: division of multiplication cross sections by keff , variation of boron acid concentration, variation of reactor power. If a transient calculation should be carried out, the following perturbations can be treated: movements of single control rods or control rod bank, variation of core coolant inlet temperature, variation of boron acid concentration, changes of core pressure drop or total mass flow rate, changes of pressure.
5. Known Approximations:
The detailed description of known approximations in the code DYN3D can be found in / 1 /.
6. Mathematical Model:
The 3-dimensional neutron distribution is calculated by solving the diffusion equation for two energy group with help of a nodal expansion method for hexagonal geometry. An exponential transformation technique is used for the time integration of time dependent neutron diffusion equations including the equations for delayed neutrons. An implicit difference scheme is used for time derivative expression of neutron fluxes.
The core is represented by one-dimensional parallel coolant channels. Each channel is connected to a fuel assembly. The flow model ( one- and two-phase flow ) is based on four differential balance equations for mass, energy and momentum of the mixture and mass balance of the vapour phase. The phase slip is taken into account in quasi-static manner by a slip correlation. The thermohydraulic model is closed by constitutive laws for one- and two-phase frictional pressure drops, evaporation and condensation rate, heat transfer coefficients and thermophysical properties of the phase. For the fuel rod the one-dimensional heat conduction equation is solved.
7. Features of Techniques Used:
The detailed description of features of techniques used in the code DYN3D can be found in / 1 /.
8. Computer, Operational System:
Computer: Hewlett Packard, HP Apollo 9000 Series 700, Model 710
Operational system: HP-UX 8.07
Operational memory: 32 MB RAM
1 processor
9. References:
/ 1 / U. Grundmann, U. Rohde:
DYN3D/M2 - a Code for Calculation of Reactivity Transients in Cores with Hexagonal Geometry, FZR 93-01, Reprint of Report ZfK-690, Research Centre Rossendorf Inc., Germany, January 1993
10. Results:
a, Primary:
The results are available in the file rez.txt.
For the comparison with available results see / 2 /.
/ 2 / R. Kyrki-Rajam(ki, E. Kaloinen: Results of the Third Three-Dimensional Hexagonal Dynamic AER Benchmark Problem, Proceedings of the Fifth Symposium of AER, Dobog(k(, Hungary, 15-19 October 1995, KFKI Atomic Energy Research Institute, Budapest (1995), pp. 255-286
b, Auxiliary:
11. Comparison to Recommended Solution:
No reference solution is available. It was recommended to make comparisons with all available results.
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