Computer Programs

NEA-1411 DYN3D/M2.

NEA-1411 DYN3D/M2.

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

NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES

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1. NAME OR DESIGNATION OF PROGRAM: DYN3D/M2.

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2. COMPUTERS

To submit a request, click below on the link of the version you wish to order. Rules for end-users 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

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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.

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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.

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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.

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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

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7. UNUSUAL FEATURES OF THE PROGRAM:

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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.

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9. STATUS

Package ID	Status date	Status
NEA-1411/01	05-NOV-1996	Screened

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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).

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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.

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12. PROGRAMMING LANGUAGE(S) USED

Package ID	Computer language
NEA-1411/01	FORTRAN-77

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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.

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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:

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15. NAME AND ESTABLISHMENT OF AUTHORS

          U. Grundmann, U. Rohde
          Research Center Rossendorf Inc.
          P.O.B. 19
          DO-8051 Dresden, Germany

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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

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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.