OECD/NEA Data Bank 

Computer Program Service (CPS) E-Newsletter

No. 11, December 2002 

Computer Program Service of the OECD/NEA Data Bank

The most recently acquired computer codes and data are: 

    IAEA-1391 SHIELDER Gamma shielding calculations of radionuclides emitting photons 0-5 to 10 MeV
    NEA-1627 BOT3P2.0 2D/3D, Mesh Generator and Graphical Display of Geometry and Results for Deterministic Transport Codes
    NEA-1678 BOT3P3.0 3D Mesh Generator and Graphical Display of Geometry for Deterministic & Monte Carlo Radiation Transport Codes, Display of Results
    IAEA-1388 FOTELP-PEN Photons, Electrons and Positrons Transport in 3D by Monte Carlo Techniques
    NEA-1553 SINBAD-FNS-V Neutron spectra and dosimetry, gamma-ray spectra and heating from a 25.4 cm cube of Vanadium irradiated with a D-T neutron source (FNS/JAERI clean benchmark)
    NEA-1552 SINBAD-ROESTI Hadron and low-energy neutron fluences and absorbed doses in the cascades induced in iron and lead dumps irradiated by high-energy hadron beams
    CCC-0371 ORIGEN-2.2 Isotope Generation and Depletion Code Matrix Exponential Method
    CCC-0708 REBUS-PC 1.4 Code System for Analysis of Research Reactor Fuel Cycles
    CCC-0661 SOURCES-4C Calculating Alpha, N, Fission, Delayed Neutron Sources and Spectra
    CCC-0654 VENTURE-PC 1.1 Reactor Analysis System with Sensitivity and Burnup
    IAEA1397 ZZ-WIMS-D/4LIB 61, 64, 69, 76 and 79 energy groups WIMS-D/4 libraries
    NEA-1554 ZZ-PWR-MSLB-REV.3 PWR Main Steam-Line Break Benchmarks, Coupled Neutronics Thermal-Hydraulics
    NEA-1086 TRISTAN 3-D fixed source radiation transport
    NEA-0446 DELIGHT-7 Point Reactivity Burnup for HTGR Lattice with P1 Neutron Scattering Approximation
    CCC-0537 TRIPOS Monte Carlo Ion Transport Analysis Code
    CCC-0715 MCNPX 2.4.0 Monte Carlo N-Particle Transport Code System for Multiparticle and High Energy Applications
    DLC-0205 ZZ-MCNPXDATA 2.4.0 Neutron, Photon, Electron, and Proton Data Libraries for MCNPX 2.3.0 or 2.4.0
    NEA-1640 ZZ-BWRTT BWR Turbine Trip Transient Benchmark Based on Peach-Bottom 2 (Update)
    NEA-1210 ZZ-HATCHES-15 Database for Radio Chemical Modelling
    ESTS0663 CFDLIB99.2* Computational Fluid Dynamics Library
    NEA-1684 IFPE/IFA-534.14 Fission gas release as a function of burnup at high power (52-55 MWd/kg)
    NEA-1685 IFPE/IFA-597.3 Centre-line temperature, fission gas release and clad elongation at high burn-up (60-62 MWd/kg)
    NEA-1561 CHEMENGL/CHIMISTE Chemical and Physical Properties of Elements (Update)
    IAEA1169 EMPIRE-II 2.18 Comprehensive Nuclear Model Code, Nucleons, Ions Induced Cross-Sections
    NEA-1492 NUCLEUS-CHART Interactive Chart of Nuclides (Update)
    NEA-1687 IRPHE/B&W-SS-LATTICE Spectral Shift Reactor Lattice Experiments
    NEA-1679 PVIS-4 Pressure vessel irradiation, source preparation
    NEA-1406 TOPICS-B Neutron and Gamma Cross-Sections Library Handling in FIDO Format
    NEA-0919 SRIM-2003 Stopping Power and Range of Ions in Matter
    NEA-1603 DCHAIN-SP 2001 Code System for Analyzing Decay and Build-up Characteristics of Spallation Products
    NEA-1676 ERRORJ Multigroup covariance matrices generation from ENDF/B-6 format
    NESC0983 EGUN Charged Particle Trajectories in Electromagnetic Focusing System (Update)

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

For more details see weekly updated list (on Mondays) 

  • List of the programs by subject field 
  • The list of MCNP (ACE format) libraries has  been updated. There is now a large set of such libraries available based on the most recent evaluations and for several temperatures.

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 .
  • The International Fuel Performance Experiments Database (IFPE) was recently enriched with new experiments and some evaluations of the experiments were revised. 

Workshops, Training Courses & Tutorials planned for 2003: 

  • 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 Common Tools for Deterministic Radiation Transport, for Monte Carlo and Hybrid Codes (25-26 September 2003 in connection with the conference SNA-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-2003 (electron-photon transport) training course / tutorial, (7-10 July 2003, NEA, Paris), (see previous workshop report) - here is the registration form
  • KENO / SCALE Training Courses 2003, 23-27 June 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
  • MCNP5 Intermediate/Advanced Level Training Course, 24-28 March 2003, at the Imperial College, London, England 
  • MCNP5 Training Course, date and place not yet firmly decided (France) 
  • 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
  • MCNPX training course, date and place to be determined.
  • QUADOS workshop: Intercomparison on the Usage of Computational Codes in Radiation Dosimetry,  14 - 16 July  2003, Bologna, Italy, organised by: ENEA and University of Bologna, co-sponsored by: EURADOS, OECD/NEA, Contact: Gianfranco Gualdrini guald@bologna.enea.it

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.