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OECD/NEA Data Bank

Computer Program Service (CPS) E-Newsletter

No. 3, April 2001

Computer Program Service of the OECD/NEA Data Bank


Computer Codes

The most recently acquired computer codes and data are: 
  • MECC-7, medium-energy intranuclear cascade code system (revised)
  • SONATINA, predicts behaviour of prismatic HTGR core under seismic excitation
  • MCVIEW, 3-D radiation view-factor by Monte Carlo method
  • CASKET, thermal & structural analyses for transport & storage cask
  • BWRDYN, thermal hydraulic analysis of a BWR plant 
  • PDASAC, partial differential sensitivity analysis of stiff systems 
  • MC2-2, fast neutron spectra and multigroup cross-sections calculation from ENDF/B data

For more details see weekly updated list (on Mondays)

  • We have carried out a study to determine the difficulties encountered and the effort required to export codes written in Fortran-IV and Fortran-77 to Fortran-95 compiler environments. This will help us to determine the survivability of not recently developed software accross language and system evolution. The report "Upgrading older Fortran Programs to current Fortran-95 versions" is accessible as PDF file (Acrobat Reader).
    Examples of  computer codes that were successfully upgraded to Fortran-95 in this exercise are:

  • PAPIN, cross-sections, self-shielding factors for fertile isotopes in the unresolved resonance region

  • PEPIN, fission products concentrations, activities, spectra, residual heat

  • THERMOS, 1-d integral transport for neutron spectra, slab and cylindrical geometry 

  • SASSI, total and differential elastic & inelastic neutron cross section by Hauser-Feshbach method

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  • The list of Nuclear Model Codes available from the NEA DB has been prepared with the corresponding hyperlinks. They are categorised by model type.

We keep the lists with hyperilinks specific to different topics announced in previous e-Newsletters up to date:

Integral Experiments Data for Model and Code Validation. The most recently acquired sets of integral experiments are: 
ZZ-BWRTT, BWR turbine trip transient benchmark based on Peach-Bottom 2
IFPE/DEMO-RAMP-I, II & IV pellet clad interaction behaviour, fast power ramping experiments

Compilations and evaluations have been updated concerning the :

  • International Fuel Performance Experiments Data Base IFPE

  • Shielding Experiments Data Base (SINBAD) at RSICC or NEADB


Training Courses & Tutorials:

For 2001, the following training courses, tutorials or code user group meetings are proposed :

  • MCNP introductory training course mid-September 2001 in Germany or UK,

  • TRIPOLI-3.5 (Monte Carlo) training course, (2-4 October, 2001 at NEA, Paris),

  • PENELOPE-2000  (electron-photon transport) workshop with tutorial, (November 2001, NEA, Paris),

  • NJOY  (Evaluated Nuclear Data Processing) Workshop / User Group meeting, 15 May 2001 at Aix-en-Provence, France,

  • SCALE 4.4A- Criticality, Shielding, Source Term (tentative)

  • Tutorials on deterministic radiation transport codes (tentatively early 2002)

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The proposed courses, tutorials etc. will be held depending on user interest and participation.

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