NEA-1612 PIN99W.

1. NAME OR DESIGNATION OF PROGRAM:  PIN99w.

3. DESCRIPTION OF PROGRAM OR FUNCTION

The Code is developed to describe fuel rod thermomechanical behaviour in operational conditions. The main goal of this code is to calculate fuel temperature, gap conductivity, fission gas release and inner gas pressure.

4. METHODS

- fuel rod temperature response is solved by using one
  dimensional finite element method combined with weighted
  residuals method
- the code involves models describing physical phenomena typical for
  the fuel irradiated in Light Water Power Reactors
  (densification, restructuring, fission gas release, swelling and
  relocation)
- this code is updated and improves PIN-micro code.

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

- simplified mechanistics solution
- only steady-state solution
- no cladding failure criterion
- no model for axial fuel-cladding interaction

6. TYPICAL RUNNING TIME:  Depends on computer type and input data.

7. UNUSUAL FEATURES

It is an improved version of the original computer code PIN for the MS DOS 6.2 version or later.

8. RELATED OR AUXILIARY PROGRAMS

Minimal software package: MS DOS 6.2 or later,(WIN 95/98/NT4.0 recommended) F77L-EM/32 FORTRAN77 Version 5.01 of Lahey Computer Systems, Inc.(graphic support library - graph3).

10. REFERENCES

1. Pazdera F., Valach M.:
     Programs PIN-02 and PLOT-1., UJV-5384, 1980.
2. Pazdera F., Valach M.:
     User's Guide for PIN: A Computer Program for the Calculation of
     the Thermal Behaviour of an Oxide Fuel Rod. UJV-6124T, 1982.
3. Strijov P., Yakovlev V., Dubrovnin K., Pazdera F., Valach M.,
   Barta, O.:
     An improved version of the PIN code and its verification.
     IAEA Technical Committee Meeting on Water Reactor Fuel Element
     Computer Modelling in Steady-State, Transient and Accident
     Conditions.
     Preston, England, 19-22 September 1988. IWGFPT/32
4. Strijov P. et al.:
     Research of VVER-440-type Fuel Rods in MR-reactor.
     IAEA International Symposium on Improvements in Water Reactor
     Fuel
     Technology and Utilization, Stockholm, Sweden, 15-18 Sep. 1986.
5. Strijov P., Dubrovnin K., Yakovlev V., Pazdera F.:
     Computer  and experimental VVER fuel rod modelling for extended
     burnup.
     IAEA Techical Committee Meeting on Fuel Performance at High
     Burnup
     for Water Reactors held in Studsvik, Sweden, 5-8 June 1990.
     IWGFPT/36
6. Svoboda R.: The IAEA CRP FUMEX Influence on the Fuel Rod
     Performance
     Modellng Quality in the Czech Republic, Portland, USA.

- Pavel Strizhov, Mojmir Valach:
Description of the PIN micro Innovation to the PIN99w code
NRI Rez plc english Report - UJV 11321-T,M (November 1999)

11. HARDWARE REQUIREMENTS:  IBM PC compatible, min. 16 MB RAM

13. SOFTWARE REQUIREMENTS:  MS DOS 6.2 or later.

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:  No special requirements

15. NAME AND ESTABLISHMENT OF AUTHORS

     M. Valach
     Reactor Technology Department
     Nuclear Power Safety Division
     Nuclear Research Institute Rez plc
     250 68 Rez near PRAGUE
     Czech Republic   
     
     P. Strizhov                                     
     engaged under NRI Rez plc contracts as main co-author
     IRTM of RRC "Kurchatov Institute", Kurchatov Square 1,
     MOSCOW
     Russia   
     
     R. Svoboda
     Rector Physics Department
     Temelin Nuclear Power Plant
     373 05 Temelin      
     Czech Republic

Fortran source files
Load modules
demo input files
compile files
abstract.txt abstract for PIN99w
Manual99.txt Input data preparation for the PIN99w version of the code
PINW99R8.doc Electronic documentation
PINW99R8.PDF Documentation in PDF form