last modified: 22-OCT-1996 | catalog | categories | new | search |

NEA-1411 DYN3D/M2.

DYN3D/M2, Reactivity Transients in Light H2O Reactors with Hexagonal Geometry

top ]
1. NAME OR DESIGNATION OF PROGRAM:  DYN3D/M2.
top ]
2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
DYN3D/M2 NEA-1411/01 Tested 05-NOV-1996

Machines used:

Package ID Orig. computer Test computer
NEA-1411/01 IBM 3090 Many Computers
top ]
3. DESCRIPTION OF PROGRAM OR FUNCTION

DYN3D/M2 is a computer code for calculating reactivity induced transients in light-water reactor cores with hexagonal fuel elements, including the initial steady state, in three-dimensional geometry. As results of the program, neutron fluxes and power distributions, thermo-hydraulics parameters of the coolant, fuel and cladding temperatures and some parameters for fuel rod failure estimation are given.
Boundary conditions from the primary coolant circuit (pressure, coolant flow rate and temperature) must be given as input.
top ]
4. METHOD OF SOLUTION

For solving the two-group neutron diffusion equation, a nodal expansion method in hexagonal geometry is used. In the hexagonal plane, an expansion of the neutron flux in a series of Bessel functions is made. Polynomials up to the 4th order are used for the approximation of neutron flux in axial direction. An exponential transformation technique is used for the time integration of neutron kinetics equations.
The thermo-hydraulic part of the code includes a one- or two-phase coolant flow model, a heat transfer regime map from liquid convection up to superheated steam, a fuel rod model including metal-water reaction as well as a simple estimation of mechanical behaviour and a lower plenum mixing model for WWER-440 type reactors. In the thermo-hydraulics model, implicit numerical solution techniques are used. A sophisticated time step control allows a wide range variation of time steps depending on the process behaviour.
A restart option can be used and an off-line analysis of results from extended output data files can be accomplished.
top ]
5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

In the main program  DYN3D/M2, three working arrays IARR, RARR and FTH are declared (two  of REAL type and one of INTEGER type). The necessary lengths of these arrays are problem dependent and can be estimated by rules given in the Code Manual. If the standard lengths (IARR: 25000, RRAR: 380000, FTH: 300000) are too small for the problem considered, the DIMENSION operator in the source file has to be changed.
top ]
6. TYPICAL RUNNING TIME

The sample problem with 190 spatial nodes took about 340 seconds of CPU time on the IBM 3090 computer. NEA 1411/01: The package was screened at the NEA/DB on a VAX 6000-510 computer under OpenVMS 6.1
top ]
7. UNUSUAL FEATURES OF THE PROGRAM:
top ]
8. RELATED AND AUXILIARY PROGRAMS

The neutron kinetics part of the code is based on the code HEXNOD23 also available from the NEA DATA  BANK. Moreover, a version DYN3D/M1 of the code exists, including 3D  neutron kinetics and a simple thermo-hydraulic feedback model. The program OUTGRA with subroutine REGRAF, source files of which are also delivered, can be used for off-line management of the output file and must be called separately.
top ]
9. STATUS
Package ID Status date Status
NEA-1411/01 05-NOV-1996 Screened
top ]
10. REFERENCES

- J. Hadek and U. Grundmann:
  Rod-drop in the 55 Assemblies Active Core of the LR-O Reactor.
  Comparison of Calculations and Experiment
  UJV 8855 R (Septamber 1989) (in Russian)
NEA-1411/01, included references:
- U. Grundmann and U. Rohde:
  DYN3D/M2 - A Code for Calculation of Reactivity Transients in
  Cores with Hexagonal Geometry
  ZfK-690 (November 1989).
- U. Grundmann and U. Rohde:
  The Code DYN3D/M2 for the Calculation of Reactivity Initiated
  Transients in Light Water Reactors with Hexagonal Fuel Elements
  - Code Manual and Input Data Description
  FSS-2/92 (March 1992).
- U. Rohde:
  Modelling of Fuel Rod Behaviour and Heat Transfer in the Code
  FLOCAL for Reactivity Accident Analysis of Reactor Cores
  presented at the First Baltic Heat Transfer Conference, Goeteborg,
  Sweden (26-29 August 1991).
- U. Grundmann and U. Rohde:
  3-Dimensional Analysis of an Absorber Rod Ejection Accident in the
  Reactor WWER-440 by the Code DYN3D/M2
  1st Symposium of Atomic Emergy Research, Rez near Prague,
  Czechoslovakia (23-27 September 1991).
- Lehmann et al.:
  A Fast Critical Reactor Assembly
  Kernenergie 34 (1991).
top ]
11. MACHINE REQUIREMENTS

The code runs at IBM 3090 and IBM-compatible  EC 1055 computer. A clock is required.
NEA-1411/01
The package was screened at the NEA/DB on a VAX 6000-510 under OpenVMS 6.0-1. The amount of diskspace required to hold the package files is about 0.9 MByte.
top ]
12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-1411/01 FORTRAN-77
top ]
13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
VM/CMS on IBM 3090, SVS 7.2 on EC 1055.
NEA-1411/01
The package was screened only. The source files were compiled in the VAX 6000-510 under OpenVMS-6.1 using the DEC Fortran-77 compiler.
top ]
14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
top ]
15. NAME AND ESTABLISHMENT OF AUTHORS

          U. Grundmann, U. Rohde
          Research Center Rossendorf Inc.
          P.O.B. 19
          DO-8051 Dresden, Germany
top ]
16. MATERIAL AVAILABLE
NEA-1411/01
File name File description Records
NEA1411_01.001 Information file of package DYN3D/M2 357
NEA1411_01.002 DLC Command file for installation on VAX 104
NEA1411_01.003 Source file # 1 100
NEA1411_01.004 Source file # 2 97
NEA1411_01.005 Source file # 3 89
NEA1411_01.006 Source file # 4 195
NEA1411_01.007 Source file # 5 105
NEA1411_01.008 Source file # 6 406
NEA1411_01.009 Source file # 7 261
NEA1411_01.010 Source file # 8 98
NEA1411_01.011 Source file # 9 16
NEA1411_01.012 Source file # 10 54
NEA1411_01.013 Source file # 11 58
NEA1411_01.014 Source file # 12 70
NEA1411_01.015 Source file # 13 61
NEA1411_01.016 Source file # 14 3
NEA1411_01.017 Source file # 15 49
NEA1411_01.018 Source file # 16 119
NEA1411_01.019 Source file # 17 223
NEA1411_01.020 Source file # 18 133
NEA1411_01.021 Source file # 19 407
NEA1411_01.022 Source file # 20 444
NEA1411_01.023 Source file # 21 101
NEA1411_01.024 Source file # 22 69
NEA1411_01.025 Source file # 23 145
NEA1411_01.026 Source file # 24 79
NEA1411_01.027 Source file # 25 196
NEA1411_01.028 Source file # 26 182
NEA1411_01.029 Source file # 27 70
NEA1411_01.030 Source file # 28 60
NEA1411_01.031 Source file # 29 157
NEA1411_01.032 Source file # 30 263
NEA1411_01.033 Source file # 31 45
NEA1411_01.034 Source file # 32 143
NEA1411_01.035 Source file # 33 63
NEA1411_01.036 Source file # 34 134
NEA1411_01.037 Source file # 35 66
NEA1411_01.038 Source file # 36 224
NEA1411_01.039 Source file # 37 153
NEA1411_01.040 Source file # 38 201
NEA1411_01.041 Source file # 39 176
NEA1411_01.042 Source file # 40 69
NEA1411_01.043 Source file # 41 55
NEA1411_01.044 Source file # 42 248
NEA1411_01.045 Source file # 43 17
NEA1411_01.046 Source file # 44 166
NEA1411_01.047 Source file # 45 193
NEA1411_01.048 Source file # 46 175
NEA1411_01.049 Source file # 47 293
NEA1411_01.050 Source file # 48 88
NEA1411_01.051 Source file # 49 56
NEA1411_01.052 Source file # 50 198
NEA1411_01.053 Source file # 51 135
NEA1411_01.054 Source file # 52 141
NEA1411_01.055 Source file # 53 187
NEA1411_01.056 Source file # 54 135
NEA1411_01.057 Source file # 55 197
NEA1411_01.058 Source file # 56 77
NEA1411_01.059 Source file # 57 76
NEA1411_01.060 Source file # 58 99
NEA1411_01.061 Source file # 59 80
NEA1411_01.062 Source file # 60 36
NEA1411_01.063 Source file # 61 267
NEA1411_01.064 Source file # 62 157
NEA1411_01.065 Source file # 63 235
NEA1411_01.066 Source file # 64 214
NEA1411_01.067 Source file # 65 46
NEA1411_01.068 Source file # 66 123
NEA1411_01.069 Source file # 67 76
NEA1411_01.070 Source file # 68 154
NEA1411_01.071 Source file # 69 115
NEA1411_01.072 Source file # 70 64
NEA1411_01.073 Source file # 71 445
NEA1411_01.074 Source file # 72 242
NEA1411_01.075 Source file # 73 3
NEA1411_01.076 Source file # 74 43
NEA1411_01.077 Source file # 75 273
NEA1411_01.078 Source file # 76 342
NEA1411_01.079 Source file # 77 201
NEA1411_01.080 Source file # 78 75
NEA1411_01.081 Source file # 79 43
NEA1411_01.082 Source file # 80 31
NEA1411_01.083 Source file # 81 7
NEA1411_01.084 Source file # 82 451
NEA1411_01.085 Input control data file 3
NEA1411_01.086 Data file for WWER-440 (Vers W-213) Calc. 36
NEA1411_01.087 Data file for WWER-440 (Vers W-213) Exp. 36
NEA1411_01.088 Data file for WWER-440 (Vers W-230) Calc. 36
NEA1411_01.089 Data file for WWER-440 (Vers W-230) Exp. 36
NEA1411_01.090 File with neutron kinetics data 179
NEA1411_01.091 File with thermo-hydraulic data 24
NEA1411_01.092 DOS file-names 91
top ]
17. CATEGORIES
  • F. Space - Time Kinetics, Coupled Neutronics - Hydrodynamics - Thermodynamics

Keywords: LWR reactors, fuel rods, heat transfer, hexagonal-z, neutron flux, power distribution, reactivity, reactor cores, reactor kinetics, reactor safety, thermodynamics, three-dimensional, transients, two-group theory, two-phase flow.