OECD/NEA Data Bank

Computer Program Service (CPS) E-Newsletter

No. 22, February 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 Data Bank computer program and nuclear data services celebrated their 40th anniversary in 2004. Since then more than 70 000 copies of computer program packages were distributed to about 600 establishments and scientists in member countries have also had free access to a very large collection of bibliographic, experimental and evaluated nuclear data.
More detailed statistics in graphical concerning acquisitions and distribution of computer codes during 2004 can be found here.

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

Identification Name Description
ENDF/B Format Check (Tested)
FIZCON-7.0 ENDF/B Cross-Sections Redundancy Check (Tested)
ENDF/B Thermal Cross-Sections, Resonance Integrals, G-Factors Calculation (Tested)
ENDF/B Data Consistency Check in ENDF Format (Tested)
ENDF/B Book-keeping Operations for ENDF Format Files (Tested)
radiotoxicity, activity, dose and decay power calculations for spent fuel (New)
Modeling of Geochemical Reactions, Calculation of pH, REDOX Potential (Tested)
Windows Interactive Version of PHREEQC (Tested)
code to create graphs from the data generated by PHREEQC (Tested)
KFK SNEAK Fast Reactor Experiments, Primary Documentation (Revised Edition)
Radioactive Waste Disposal Site Economic Model (Tested)
VENUS-3 LWR-PVS Benchmark Experiment  (New)
High Energy Neutron Spectra Generated by 590-MeV Protons on a Thick Lead Target (New)
SINBAD-IPPE-FE IPPE neutron transmission benchmark experiment with 14 MeV neutrons through iron shells (New)
MCB Continuous-Energy Neutron Cross Section Libraries for Temperatures from 300 to 1800 K (DVD version)
MCB Continuous-Energy Neutron Cross Section Libraries for Temperatures from 300 to 1800 K (DVD version)
Behaviour of 3 BWR segments FK-1, FK-2 & FK-3 under RIA test conditions in NSRR (New)

For more details see weekly updated list (on Mondays)

Integral Experiments Data for Model and Code Validation:

The home page for Compilations and Evaluations has been updated concerning:
  • A revised edition of the format in which the International Reactor Physics Experiments Evaluation Project( IRPhE ) data are presented and guidelines for compilation, evaluation and review (Revision 8.8) was issued recently.
  • The International Fuel Performance Experiments Database (IFPE) was recently updated with new experiments and contains now 831 cases (28 February 2005).
  • The Shielding Benchmark Experiments Database (SINBAD) includes now 35 Reactor Shielding, 26 Fusion Neutronics Shielding and 9 Accelerator Shielding Experiments. (last update: 15 December 2004).
  • 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 now 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
      • NJOY Workshop and User Group Meeting, 2 May 2005, NEA headquarters, 12 boulevard des Iles , 92130 Issy les Moulineaux, France
      • 4-7 July 2005, Scope & Objectives and Syllabus, Registration Form.
      • Workshop on Using MCNP5 for Medical Physics Applications, sponsored by Computational Medical Physics Working Group on Sunday, April 17, 2005, 1-5pm.  Participation is free. It is held in conjunction with the Monte Carlo 2005 Conference; Chattanooga Convention Center, Chattanooga, Tennessee, USA.
      • Seminar and Training on Scaling, Uncertainty and 3D Coupled Code Calculations in Nuclear Technology, 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 at LANL (see also: http://mcavignon2005.cea.fr/ )
      • 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/)
      • APOLLO2 Workshop, Avignon, 15 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/)
      • 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
  • Meetings Sponsored by the Nuclear Science Committee & Data Bank
      Meetings scheduled

    • 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

    • 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

    • 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


    • 2-5 April 2006
      2006 Biennial Radiation and Shielding Topical Meeting (RPS 2006)
      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

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