OECD/NEA Data Bank

Computer Program Service (CPS) E-Newsletter

No. 26, December 2005

Computer Program Service of the OECD/NEA Data Bank
  1. New computer codes related information
  2. Integral Experiments
  3. Workshops, training courses tutorials, meetings

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

Identification Name Description
MEPhI empty slits streaming experiment (1995-1998) (New)
MC Codes for Neutron Photon Transport Calc. based on Continuous Energy and Multigroup Methods (New)
Radioactive Surface Contamination Investigation Program
Estimation of dose-rates reduction by garden decontamination
IFPE/HATAC Fission Gas Release at High Burn-up, Effect of a Power Cycling (New)
EPICSHOW Interactive Viewing of EPIC (Electron Photon Interaction Code) Data Library (Tested)
FOTELP-2K3 Photons, Electrons and Positrons Transport in 3D by Monte Carlo Techniques (Tested)
XNWLUP Graphical user interface to plot WIMS-D library multigroup cross sections (Tested)
NRCPIPES Fracture Mechanics of Cracked Pipes (Tested)
HABIT Toxic and Radioactive Release Hazards in Reactor Control Room (Tested)
IAEA0940/01 JADSPE Multi-Channel Gamma Spectra Unfolding Program (Tested)
IAEA1401/01 ZZ DROSG-2000 Legendre Coefficient Library for 59 monoenergetic neutron source reactions (Tested)
IAEA1402/03 ENDVER-ENDVER/GUI The ENDF File Verification Support Package (Tested)
ZZ RRDF-98 Cross-sections and covariance matrices for 22 neutron induced dosimetry reactions (Tested)
ZZ-MINSKACT Evaluated neutron reaction data for Th-232, Pa, U, Np, Pu, Am and Cm isotopes (Tested)
CALENDF-2002 Pointwise, Multigroup Neutron Cross-Sections and Probability Tables Production from ENDF/B Evaluations (Tested)
DORTDAT2 Input-Making Support System for a Two-Dimensional SN Code, DORT (Tested)
ERRORJ Multigroup covariance matrices generation from ENDF-6 format (Tested)
IRPHE-KNK-II-ARCHIVE KNK-II fast reactor documents, power history and measured parameters (New)
IAEA1419/01 ZZ IBANDL Ion Beam Analysis Nuclear Data Library in R33 format (Tested)
IAEA1418/01 ZZ INDL/TSL Thermal Neutron Scattering Data for H2O, D2O and ZrHx in ENDF-6 Format and as MCNP(X) Data Sets (Tested)
ESTS0219/07 TOUGHREACT Chemically reactive non-isothermal flows of multiphase fluids in porous and fractured media (New)
ESTS0219/08 TMVOCV1.0
Multicomponent, multiphase, nonisothermal flows of water (New)

For more details see daily updated list

Integral Experiments Data for Model and Code Validation:

The home page for Compilations and Evaluations has been updated concerning:
  • The International Fuel Performance Experiments Database (IFPE) contains 851 cases (21 October 2005).
  • The Shielding Benchmark Experiments Database (SINBAD) includes 36 Reactor Shielding-27 Fusion Neutronics Shielding-, and 13 Accelerator Shielding-Experiments. (last update: 16 December 2005).
  • The experimental data and reports from recent projects operated under the auspices of the Committee on the Safety of Nuclear Installations (CSNI) have been added to the Data Bank. (These comprise the CABRI project, the SETH Project and the PSB-VVER Project). These data are subject to restrictions for their distribution.

Workshops, training courses tutorials planned for 2006:

  • Courses / Workshops
    • For 2006
      • Further announcements for possible courses on MCNP5, MCNPX, SCALE5, TRIPOLI-4 and others will be made later. Future courses, tutorials etc. will be held depending on user interest and participation.
      • 23 January - 10 February 2006
        Seminar and Training on Scaling, Uncertainty and 3D Coupled Code Calculations in Nuclear Technology, (3D.S.UNCOP-2005), School of Nuclear Engineering, Barcelona, Spain

      • 7-8 April 2006
        Training Course on Neutron Spectra Unfolding, Cape Town, South Africa: UMG software package provided by PTB (UMG: Unfolding with GRAVEL and MAXED)

      • 15-17 May 2006
        TOUGH Symposium 2006, Lawrence Berkeley National Laboratory, Berkeley, California

      • PENELOPE-2006 Barcelona, early July 2006, (programme is being prepared).

      • 15-17 September 2006
        Workshop on Use of Monte Carlo Techniques for Design and Analysis of Radiation Detectors, University of Coimbra, Coimbra, Portugal
    • Courses / Workshops recently held
      • NJOY Workshop and User Group Meeting, 2 May 2005, NEA headquarters, 12 boulevard des Iles , 92130 Issy les Moulineaux, France (Proceedings)
      • PENELOPE 4-7 July 2005, Scope Objectives and Syllabus
      • Seminar and Training on Scaling, Uncertainty and 3D Coupled Code Calculations in Nuclear Technology, (3D.S.UNCOP-2005) University of Zagreb, 20 June - 8 July 2005
      • Workshop on Advances in Monte Carlo Criticality Calculations, Avignon, France, 11 September 2005. This workshop has focussed on recent advances in methods, codes, and data for Monte Carlo criticality calculations, including: improvements to MCNP5 kcode calculations, source entropy as a convergence diagnostic, Weilandt acceleration, stochastic geometry for HTGRs, use of mesh tallies for reactor applications, pre-ENDF/B-VII data, Doppler broadening, material composition library, etc. Presenters will be Forrest Brown Russell Mosteller from the MCNP development team, X5 at LANL
      • Workshop on the Monte Carlo Code TRIPOLI-4 , Avignon, France, 11 September 2005, by the TRIPOLI-4 team. The TRIPOLI-4 Monte Carlo transport code (neutron, gamma, electron/positron) is dedicated mainly to shielding, core physics and criticality studies. The workshop will be centered on the following topics:
        • description of the main capabilities/characteristics: geometry, material, source,
        • cross-sections, biasing techniques, estimators/scoring, …
        • overview on programming features: language, architecture, parallelism
        • overview on validation: experimental benchmarks and inter-code comparisons
        Presentation of some realistic studies carried out with TRIPOLI-4 and of future functionalities.
      • APOLLO2 Workshop, Avignon, 11 September 2005 from 1.30 PM to 4.30 PM presented by Igor Zmijarevic APOLLO2 team members (CEA). Apollo2 is a widely used, general purpose transport code for assembly and core calculations. This workshop will give an overall view of the models implemented in the code and focus on recent developments, such as in self-shielding formalism, acceleration techniques for the method of characteristics, multigroup calculation in a large number of groups, 2D core calculations, etc. The qualification program of Apollo2 will be presented together with some recent applications.
      • Workshop on Processing of Application Libraries for Monte Carlo Transport Calculations, 12-16 September 2005, IAEA, Vienna, Austria
      • On request, the handouts of the Workshop on Advances in Monte Carlo Criticality Calculations, and Workshop on the Monte Carlo Code TRIPOLI-4 are available on CD-ROM to authorised users from NEA Data Bank member countries
      • Workshop on Evaluation of Uncertainties in Relation to Severe Accidents and Level 2 Probabilistic Safety Analysis, Cadarache (France), 7-9 November 2005

  • Meetings Sponsored by the Nuclear Science Committee Data Bank


      • 3-6 April 2006
        14th Biennial Topical Meeting of the ANS Radiation Protection and Shielding Division
        General Chair: Dr. Chuan Fu Wu (Department of Energy)
        Technical Program Chair: Dr. Robert Hayes (Westinghouse TRU Solutions)
        Carlsbad, New Mexico, USA

      • 22-24 May 2006
        Shielding Aspects of Accelerators, Targets and Irradiation Facilities - SATIF-8

        Chair: Hee-seock LEE
        Pohang Accelerator Laboratory POSTECH, Korea, Rep.

      • 5-7 September 2006
        CFD4NRS: Workshop on Benchmarking of CFD Codes for Application to Nuclear Reactor Safety,
        OECD/NEA and IAEA, hosted by Gesellschaft für Anlagen- und Reaktorsicherheit (GRS), Garching, Munich, Germany

      • 10-14 September 2006
      • PHYSOR-2006-Topical Meeting Advances in Nuclear Analysis and Advances in Nuclear Analysis and Simulation
        Hyatt Regency Vancouver
        General Chair: Ben Rouben(Atomic Energy of Canada Ltd.)
        Technical Program Chair: Dr. Kenneth S. Kozier (Atomic Energy of Canada Ltd.)
        Vancouver, Canada
        Call for Papers (PDF)

      • 25-29 September 2006
        9th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation
        (co-organised NSC/NDC)
        Nîmes, France

      • 1-4 October 2006
        3rd International Topical Meeting on High Temperature Reactor Technology - HTR 2006,
        Potchefstroom, South Africa


      • 15-18 April 2007
        SNA-2007 + MC-2007, Joint International Conference on Mathematics Computation and Supercomputing in Nuclear Applications
        Monterey Marriott, Monterey, California, USA
        General Chair: Tomas Diaz de la Rubia and Brian Wirth (Lawrence Livermore National Laboratory)
        Technical Program Chair: Jasmina Vujic (University of California, Berkeley)
        Monterey, California, USA
        Contact: Doug Vogt
      • 22-27 Avril 2007
        Nuclear Data Conference ND-2007 Nice, France

      • 28-31 May 2007
        Eighth International Conference on Nuclear Criticality Safety - ICNC-2007
        Saint Petersburg, Russia


      • 14-18 September 2008
        PHYSOR-2008- Nuclear Power: A Sustainable Energy Resource
        Interlaken, Switzerland

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