last modified: 04-JUL-1986 | catalog | categories | new | search |

IAEA0885 DRUCK.

DRUCK, Thermal, Mechanical Stress of PWR Fuel Rod During LOCA Blowdown

top ]
1. NAME OR DESIGNATION OF PROGRAM:  DRUCK.
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
DRUCK IAEA0885/01 Tested 04-JUL-1986

Machines used:

Package ID Orig. computer Test computer
IAEA0885/01 BESM-6 IBM 3081
top ]
3. DESCRIPTION OF PROBLEM OR FUNCTION

DRUCK calculates the thermal and mechanical behavior of the fuel and cladding in a nuclear fuel rod of PWR during the blow-down-phase of the LOCA and investigates if the cladding bursts.
top ]
4. METHOD OF SOLUTION

The pressure in the fuel rod is a function of temperature, void volumes and of gas atoms.
The radial temperature profile is obtained by steady-state solution  of one-dimensional equation for heat conduction.
The thermo-hydraulic conditions of the primary circuit by the accident are to assume.
Fuel and cladding dimensions (creep) and the burst temperature are calculated from empirical models.
It is assumed, that the number of gas atoms is constant under accident conditions.
top ]
5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

In the actual version of the program there are 20 variable-length axial regions of the fuel rod, 10 radial nodes of fuel and 50 time-steps.
top ]
6. TYPICAL RUNNING TIME

Usually a running time of 3 seconds per time- step are required.
IAEA0885/01
NEA-DB executed the test case included in this package  on an IBM 3081 computer in 3 seconds of CPU time.
top ]
7. UNUSUAL FEATURES OF THE PROGRAM:
top ]
8. RELATED AND AUXILIARY PROGRAMS

There is necessary a program for input data for begin of accident and a program for data for conditions in the primary circuit.
top ]
9. STATUS
Package ID Status date Status
IAEA0885/01 04-JUL-1986 Tested at NEADB
top ]
10. REFERENCES

- Untersuchungen zum Verhalten von Brennstaeben in Druckwasser-
  reaktoren beim Normalbetrieb und nach dem Bruch einer Hauptum-
  waelzleitung im kalten Strang
  Diss., TU Dresden, 1983, WB Kernenergetik.
IAEA0885/01, included references:
- Sabine Kretschmer:
  DRUCK: A Computer Program for Modelling the Complex Fuelrod
  Behaviour in Accident Conditions - Program Description
  TU Dresden, Internal Report (in german) (August 1985)
top ]
11. MACHINE REQUIREMENTS:  About 8,5 Words memory is required.
IAEA0885/01
To run the test case of the package on an IBM 3081, 180K bytes of main storage were required.
top ]
12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA0885/01 FORTRAN-IV
top ]
13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  BAMOS.
IAEA0885/01
MVS/SP (IBM 3081).
top ]
14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
top ]
15. NAME AND ESTABLISHMENT OF AUTHOR

Kretschmer, S.
Sektion Energieumwandlung
Technische Universitaet Dresden
German Democratic Republic
top ]
16. MATERIAL AVAILABLE
IAEA0885/01
File name File description Records
IAEA0885_01.001 Information file 47
IAEA0885_01.002 DRUCK source (FORTRAN 77) 953
IAEA0885_01.003 JCL to run sample case 53
IAEA0885_01.004 Sample case input 13
IAEA0885_01.005 Sample case output 481
top ]
17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: blowdown, cladding, fuel rods, loss-of-coolant accident.