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IAEA0900 STOFFEL-1.

STOFFEL-1, Steady-State In-Pile Behaviour of Cylindrical H2O Cooled Oxide Fuel Rod

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1. NAME OR DESIGNATION OF PROGRAM:  STOFFEL-1.
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2. COMPUTERS
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Program name Package id Status Status date
STOFFEL-1 IAEA0900/01 Tested 22-JUL-1986

Machines used:

Package ID Orig. computer Test computer
IAEA0900/01 ES-1055 IBM 3084Q
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3. DESCRIPTION OF PROGRAM OR FUNCTION

The STOFFEL-1 code is designed  to predict the in-pile behaviour of a cylindrical water-cooled oxide fuel rod during quasistationary operation. The code considers particularly
- the radial power density distribution due to thermal flux   depression and plutonium formation,
- radial heat transfer through the fuel, gap, and cladding to the   coolant,
- thermoelastic mechanical analysis of fuel and cladding based on  generalized plane strain approximation taking into account plastic   and creep deformations, fuel cracking and crack healing,   anisotropic behaviour of cladding material,
- fuel irradiation and thermally induced densification depending on    fuel microstructure,
- fuel grain growth and pore migration,
- fission gas behaviour on the basis of gas atom diffusion to the  grain boundaries, generation, growth, and resolution of  intragranular bubbles, growth and interlinkage of grain boundary  bubbles, swelling due to fission gas bubbles and solid fission   products.
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4. METHOD OF SOLUTION

The fuel rod to be analysed is divided into axial and radial nodes. The one-dimensional equation for radial heat conduction and LAME's equation for the strain - stress distribution  are solved at each axial node. The coupled effects of the response parameters are treated by iterating to convergence at each power- time step.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

There are no restrictions on the number of nodes or power - time steps. The smallest time step determined by the integration procedure for the creep deformation calculation is restricted to 1 seccond.
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6. TYPICAL RUNNING TIME

The code requires about 3 minutes CPU-time on a EC 1055 per one axial section and per 1000 hours of reactor operation. For runs with strongly varying power history the time required depends on the complexity of the specified operational history. The running time is correspondingly increased with the number of axial sections.
IAEA0900/01
NEA-DB executed the test case included in the package on an IBM 3084Q computer in 143 seconds of CPU time.
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7. UNUSUAL FEATURES OF THE PROGRAM

Most of the modules of the code are based on mechanistic models, especially those for fission gas behaviour calculation, densification, and power density distribution. The code enables the calculation of power ramps with various ramp rates. To save running time the code contains some options for reducing the complexity of the analysis, e.g. to perform only a thermoelastic mechanical analysis.
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8. RELATED AND AUXILIARY PROGRAMS:
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9. STATUS
Package ID Status date Status
IAEA0900/01 22-JUL-1986 Tested at NEADB
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10. REFERENCES

- D. Reinfried,
  A Simple Microstructure-dependent Model for In-Reactor
  Densification of U02
  Kernenergie 25 (1982) 210.
- D. Reinfried,
  Zur Berechnung der Brennstofftemperaturverteilung in LWR -
  Brennstaeben bei hoeheren Abbraenden.
  Kernenergie 26 (1983) 292.
- D. Reinfried,
  Modellmaessige Beschreibung des Verhaltens stabiler gasfoermiger
  Spaltprodukte in U02-Reaktorbrennstoff.
  Kernenergie 27 (1984) 151.
- D. Reinfried, H. Steinkopff,
  Performance Analysis of VVER-Type Fuel Rods with the STOFFEL-1
  Computer Code,
  Report ZKF-522, March 1984.
- D. Reinfried,
  Zur mathematischen Modellierung des Bestrahlungsverhaltens von
  Druckwasserreaktor-Brennstaeben.
  Dissertation A, Akademie der Wissenschaften der DDR,
  ZKF Rossendorf, 1984.
IAEA0900/01, included references:
- Dieter Reinfried:
  User Manual for the Fuel-Rod Modelling Program STOFFEL-1.
  ISSN 0138-2950  (June 1984) (In German)
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11. MACHINE REQUIREMENTS

To run the program on a EC 1055 computer requires 384K-bytes main storage.
IAEA0900/01
400K bytes of main storage are required on an IBM 3084Q computer.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA0900/01 PL/I
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  OS/EC.
IAEA0900/01
MVS VS2 03.8 (IBM 3084Q).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

D. Reinfried,
Akademie der Wissenschaften der DDR
Zentralinstitut fuer Kernforschung Rossendorf
Postschliessfach 19
DDR-8051 DRESDEN
Federal Republic of Germany
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16. MATERIAL AVAILABLE
IAEA0900/01
File name File description Records
IAEA0900_01.001 Information file 75
IAEA0900_01.002 JCL for compilation and linking 119
IAEA0900_01.003 JCL for running the sample problem 16
IAEA0900_01.004 STOFFEL-1 Source (PL/I) input for IEBUPDTE 2773
IAEA0900_01.005 Sample problem input 56
IAEA0900_01.006 Sample problem output 2145
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17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics
  • H. Heat Transfer and Fluid Flow
  • I. Deformation and Stress Distributions, Structural Analysis and Engineering Design Studies

Keywords: burnup, cladding, cracking, creep, deformation, fuel rods, heat transfer, mechanical properties, performance, plasticity, plutonium isotopes, power distribution, pwr reactors, strains, stresses, swelling, temperature distribution, thermal expansion, uranium 235, uranium 238, xenon.