OECD/NEA Data Bank

Computer Program Service (CPS) E-Newsletter

No. 24, July 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
  4. Thermochemical Database (TDB)
  5. Nuclear Data News 

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

Identification Name Description
IFPE/US-PWR-16X16 LTA (lead test assembly) Extended Burnup Demonstration Program (New)
SINBAD-ISIS800 ISIS Benchmark Experiment on Deep-Penetration Neutrons through Concrete and Iron Shields (1998) (New)
PASCAL Probabilistic Fracture Mechanics Analysis of Structural Components in Aging LWR (New)
IFPE/IFA-534.14REV1 Fission gas release as a function of burnup at high power (52-55 MWd/kg) (New)
W-SHIELDER calculates shielding thickness of water for photon emitting radionuclide between 0.5 to 10 MeV (New)
ZZ MATJEF22.BOLIB JEF-2.2 Multigr Coupled (199n + 42gamma) X-Section Lib. in MATXS Fmt for Nuclear Fission Applications (New)
GRTUNCL-3D/R-THETA-Z Code to Calculate Semi Analytic First Collision Source and Uncollided Flux in an R-theta-Z grid (New)
BOT3P5.0 3D Mesh Generator and Graphical Display of Geometry for Radiation Transport Codes, Display of Results (New)
EASY-2003 European Neutron Activation System (New)
ZZ V1000CT-1&2 VVER-1000 Main Coolant Pump (MCP) Switching On Benchmark (Revised Edition)

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) was updated with new experiments and contains now 851 cases (1 June 2005).
  • The Shielding Benchmark Experiments Database (SINBAD) includes now 35 Reactor Shielding, 26 Fusion Neutronics Shielding and 12 Accelerator Shielding Experiments. (last update: 14 June 2005). A new version will be included in the near future.
  • 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 REPNa series , the SETH Project and the PSB-VVER Project ). These data are subject to restrictions for their distribution at this stage. The reports and data from the RASPLAV project are available to organisations from OECD member countries and from the Russian Federation

Workshops, training courses & tutorials planned for 2005:

  • Courses / Workshops
    •  Training Courses for 2005
      • PENELOPE 4-7 July 2005, Scope & Objectives and Syllabus, Registration Form .
      • 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 will focus 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 (see also:http://mcavignon2005.cea.fr/workshops_monte_carlo.htm)
      • 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.  (see also: http://mcavignon2005.cea.fr/workshop_tripoli.htm)
      • 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. (see also: http://mcavignon2005.cea.fr/workshops_apollo.htm)
      • Workshop on Processing of Application Libraries for Monte Carlo Transport Calculations, 19-23 September 2005, IAEA, Vienna, Austria
      • Workshop on Evaluation of Uncertainties In Relation to Severe Accidents and Level 2 Probabilistic Safety Analysis, Cadarache (France), 7-9 November 2005
      • 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.
    • Workshops recently held
      • NJOY Workshop and User Group Meeting, 2 May 2005, NEA headquarters, 12 boulevard des Iles , 92130 Issy les Moulineaux, France (Proceedings)
  • Meetings Sponsored by the Nuclear Science Committee & Data Bank
      Meetings scheduled

    • 21-26 August 2005
      ICENES 2005 – 12th International Conference on Emerging Nuclear Energy Systems

      Metropole Hotel, Brussels, Belgium

    • 28 August - 1 September 2005
      Accelerator Applications - AccApp’05

      San Servolo, Venice,  Italy

    • 12-15 September 2005
      Topical Meeting Mathematics & Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications - M&C 2005

      Avignon, Palais des Papes, France
    • 19-23 September 2005
      Sixth International Conference on WWER Fuel Performance, Modelling and Experimental Support
      Albena, Bulgaria

    • 2-6 October 2005
      Nureth 11 - Nuclear Reactors Thermal-Hydraulics
      SFEN and SFANS (French section of the American Nuclear Society) in cooperation with CEA
    • 9-13 October 2005
      7th International Conference GLOBAL 2005
      Tsukuba, Ibaraki-ken, Japan

    • Meetings held

    • 16-18 February 2005
      Advanced Reactors with Innovative Fuels - ARWIF-2005

      Oak Ridge, USA

    • 17-21 April 2005
      ANS International Conference “Monte Carlo 2005” -

      The Monte Carlo Method: Versatility Unbounded in a Dynamic Computing World,
      Chattanooga, Tennessee, USA

    • 8-13 May 2005
      The Twelfth International Symposium on Reactor Dosimetry

      Park Vista Resort in Gatlinburg, Tennessee, USA
    • 15-19 May 2005
      2005 International Congress on Advances in Nuclear Power Plants (ICAPP’05)

      Grand Inter-Continental Seoul, Korea

    • 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.

    • 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)

Update from the Thermochemical Database Project (TDB):

Two new reviews were published in April by the Thermochemical Database Project (TDB): Chemical Thermodynamics of Nickel and Chemical Thermodynamics of Selenium. The TDB database has been consequently updated with new files which can be downloaded from the NEA website by registered users.
Registered users can access the new data files at the TDB webpage. Previous volumes in the series examined the chemical thermodynamics of Uranium, Neptunium, Plutonium, Americium and Technetium.
For more information, contact the TDB Project Coordinator: tdb@oecd-nea.org

Nuclear Data News:

The JEFF-3.1 Nuclear Data Library is the latest version of the Joint Evaluated Fission and Fusion Library. The complete suite of data was released in May 2005, and contains general purpose nuclear data evaluations compiled at the NEA Data Bank in co-operation with several laboratories in NEA Data Bank member countries. JEFF-3.1 contains also radioactive decay data, activation data and fission yields data. It combines the efforts of the JEFF and EFF Working Groups who have contributed to this combined fission and fusion file.
  • The complete JEFF-3.1 Library suite contains:
  • Incident Neutron Data for 381 materials from 1-H-1 to 100-Fm-255
  • Thermal Scattering Data for 9 materials
  •  Incident Proton Data for 26 materials
  •  Radioactive decay data for 3852 isotopes
  • Neutron Induced Fission Yields Library
  • Spontaneous Fission Yields Library
  • Activation Library
The library can be downloaded in its entirety as a single file or one file per isotope from the web: http://www.oecd-nea.org/dbdata/. A CD-ROM of the complete library can also be requested free of charge. contact: data@oecd-nea.org

News from the OECD Nuclear Energy Agency (NEA)

The latest issue of the NEA on-line bulletin.