OECD/NEA Data Bank 

Computer Program Service (CPS) E-Newsletter

No. 10, September 2002 

Computer Program Service of the OECD/NEA Data Bank Computer Codes

The most recently acquired and / or tested computer codes and data are: 

    NEA-1657 ANL-BPB Argonne National Laboratory Code Center Benchmark Problem Book (Arrived and tested)
    IAEA-1202 EQUIVA Few-Group Diffusion Parameter for PWR Reflector Region by 1-D Transport Calculation (Now tested)
    IAEA-1175 GRAP Gamma-Ray Level-Scheme Assignment (Now tested)
    IAEA-0886 INTERTRAN-II INTERTRAN-I and INTERTRAN-II, Radiation Exposure from Vehicle Transport of Radioactive Material (Arrived and tested)
    NEA-1451 MUTIL Asymmetry Factor of Mott Cross-Sections for Electron, Positron Scattering (Now tested)
    NEA-1422 NESKA Electron and Positron Scattering from Point Nuclei (Now tested)
    IAEA-1384 NKE Nuclide Explorer tool for retrieving interactively detailed data on radionuclides properties (Arrived and tested)
    CCC-0702 ORIGEN-ARP 2.00 Isotope Generation and Depletion Code System-Matrix Exponential Method with GUI and Graphics Capability (Arrived)
    USCD-1205 PCNULIB PCNUDAT-PCNULIB, Nuclear Properties Data Base and Retrieval System (Arrived and tested)
    NEA-1675 PPICA Power Plant Investment Cost Analysis (Arrived and tested)
    CCC-0553 RASCAL 3.0.3 Radiological Doses from Accidental Release to Atmosphere (Arrived)
    PSR-0158 SAMMY-M6B Resonance Parameters from Experimental Neutron Cross Section by R-Matrix Theory (Arrived)
    NEA-1239 SFERXS Photoabsorption, Coherent, Incoherent Scattering Cross-Sections Function for Shielding (Now tested)
    IAEA-1395 XNWLUP1.1 Graphical user interface to plot WIMS-D library multigroup cross sections (Arrived and tested)
    USCD-1208 CHECKR-6.13 ENDF/B Format Check (Arrived)
    USCD-1209 FIZCON-6.13 ENDF/B Cross-Sections Redundancy Check (Arrived)
    USCD-1210 GETMAT-6.13 ENDF/B Material Retrieval (Arrived)
    USCD-1212 INTER-6.13 ENDF/B Thermal Cross-Sections, Resonance Integrals, G-Factors Calculation (Arrived)
    USCD-1214 LISTEF-6.13 ENDF/B Data File Summary List (Arrived)
    USCD-1215 PLOTEF-6.13 ENDF/B Data Plot (Arrived)
    USCD-1216 PSYCHE-6.13 ENDF/B Data Consistency Check in ENDF Format (Arrived)
    USCD-1217 SETMDC-6.13 Preprocessor for CHECKR, FIZCON, INTER, etc. ENDF Utility source codes (Arrived)
    USCD-1218 STANEF-6.13 ENDF/B Bookkeeping Operations for ENDF Format Files (Arrived)
    DLC-0210 ZZ-CANDULIB-AECL Burnup-Dependent ORIGEN-S Cross-Section Libraries for CANDU Reactor Fuels (Now tested)
    DLC-0208 ZZ-ELAST2 Database of Cross Sections for the Elastic Scattering of Electrons and Positrons by Atoms (Now tested)
    DLC-0187 ZZ-HILO86R 66 Neutron, 22 Gamma Group Cross-Section for 400 MeV Neutron, 20 MeV Gamma (Now tested)
    NEA-1643 MCB1C Monte-Carlo Continuous Energy Burnup Code (Arrived and tested)
    DLC-0200 ZZ-MCB-DLC200 ZZ MCNPDATA, Standard Neutron, Photon and Electron Data Libraries for MCNP-4C and MCB1C (Arrived and tested)
    NEA-1668 ZZ-MCB-EAF99 MCB Continuous-Energy Neutron Cross Section Libraries for Temperatures from 300 to 1800 K (Arrived and tested)
    NEA-1669 ZZ-MCB-ENDF/B-6.8 MCB Continuous-Energy Neutron Cross Section Libraries for Temperatures from 300 to 1800 K (Arrived and tested)
    NEA-1667 ZZ-MCB-JEF2.2 MCB Continuous-Energy Neutron Cross Section Libraries for Temperatures from 300 to 1800 K (Arrived and tested)
    NEA-1670 ZZ-MCB-JENDL-3.2 MCB Continuous-Energy Neutron Cross Section Libraries for Temperatures from 300 to 1800 K (Arrived and tested)
    DLC-0212 ZZ-POINT2000 Linearly Interpolable ENDF/B-VI.7 Data for 8 Temperatures (Now tested)
    DLC-0192 ZZ-POINT97 Temperature-Dependent ENDF/B-6 Cross-Sections at 8 Temperature Between 0K and 2100K (Now tested)

Note: All computer code documentation has now been scanned and will be distributed exclusively on the CD-ROM in electronic format with the program package. No paper copies of manuals will be provided as from now. 

For more details see weekly updated list (on Mondays) 

Integral Experiments Data for Model and Code Validation

Compilations and evaluations have been updated concerning the :
  • Shielding Experiments Data Base (SINBAD) at NEADB or RSICC 
  • Work is in progress on the International Reactor Physics Benchmark Experiments Project. See IRPhE . Here you can download a recent summary (July 2002).
  • The International Fuel Performance Experiments Database (IFPE) was recently enriched with new experiments and some evaluations of the experiments were revised. 

Training Courses & Tutorials: 

     Recently completed Workshops / Courses
  • Workshop on Computing Radiation Dosimetry (CRD-2002) with embedded training course on MCNPX - Monte Carlo Code System for Multiparticle & High Energy Applications, was held at the Instituto Tecnologico e Nuclear (ITN), Sacavem, Lisbon, Portugal 22-28 June 2002.

  • The MCNPX specific training was held from 24-28 June. The Workshop proceedings will be printed in the autumn 2002. More details are provided in the CRD-2002 Web page
  • MCNP - Introductory Course including MCNP5 Features, from 9-13 September 2002 at the University of Stuttgart, Germany
For 2002 the following training courses/workshops are planned: 
  • MCNPX Training course 18-22 November 2002 at SCK.CEN Club-House Salon 2, Mol, Belgium 
  • Note that the SCALE Physor 2002 Workshop in Korea was cancelled
For 2003 the following training courses/workshops are planned: 
  • 2nd International Workshop on 'Advanced radiation transport simulation with PENELOPE (electron-photon transport)', to be held in Salou (Tarragona) from 8-10 January 2003.(Penelope User Group meeting)
  • Workshop on deterministic radiation (DT) transport codes (tentatively early 2003). The intention is to present in particular recently developed tools for modelling 3D problems, including in particular automated mesh generation, (X-Y-Z), (R-THETA-Z) and the visualisation of the corresponding results to facilitate interpretation and for improved documentation.  Presentation and discussion of methods and ideas for ensuring that the same models are used in MC and DT for benchmarking; development of compatible and common mesh generation and visualisation tools for MC and DT; Methods for 3D Sensitivity Analysis / Uncertainty Analysis should also be demonstrated. The Data Bank Executive Group has strongly recommended the development of such tools. If you are interested in participating, please fill in the form.
  • PENELOPE-2001  (electron-photon transport) training course / tutorial, (March or April 2003, NEA, Paris), (see previous  workshop report)
  • KENO / SCALE Training Courses 2003, April / May 2003 in Paris France 
  • SAMMY Workshop (analysis of experimental neutron-induced cross-section data for extracting values and covariances for resonance parameters), May 12-16, 2003, Knoxville, TN, USA (letter by the author)
  • MCNP5 Training Course(1 or 2), date and place not yet firmly decided (France / UK / Germany) 
  • AMPX-2000 Cross-Section Processing System (summer, autumn 2003), Issy-les-Moulineaux, France. (proposed programme)
  • TOUGH Symposium ,  Lawrence Berkeley National Laboratory (LBNL), 5-7 May May 5-7A symposium on applications and enhancements of  TOUGH (A General-Purpose Numerical Simulator for Multiphase Fluid and Heat Flow) with oral and poster presentations. Proceedings on CD-ROM will be available at the Symposium.

  • Contact: Stefan Finsterle, George J. Moridis, Curtis M. Oldenburg, Yu-Shu Wu LBL, E-mail: SAFinsterle@lbl.gov

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

Meetings Sponsored by the Nuclear Science Committee

Meetings scheduled for the next two years and of interest to clients of the Computer Program Service 

News from the OECD Nuclear Energy Agency (NEA) 

The latest issue of the NEA online bulletin.