IAEA0900 STOFFEL-1.
STOFFEL-1, Steady-State In-Pile Behaviour of Cylindrical H2O Cooled Oxide Fuel Rod
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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| 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.
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.
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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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.
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.[ top ]
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.
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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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.
- 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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IAEA0900/01
400K bytes of main storage are required on an IBM 3084Q computer.[ top ]
IAEA0900/01
MVS VS2 03.8 (IBM 3084Q).[ top ]
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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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- 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.