OECD/NEA Data Bank

Computer Program Service (CPS) E-Newsletter

No. 31, December 2006



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

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

 
Identification Name Description
NEA-1517
SINBAD-NAIADE-H2O-60
Fission neutron propagation in light water source diameter 60 cm (New)
NEA-1517
SINBAD-NAIADE-FE-C60
Fission neutron propagation in iron and graphite source diameter 60 cm (New)
NEA-1278
CALENDF-2005
Pointwise, Multigroup Neutron Cross-Sections and Probability Tables from ENDF/B Evaluations (New)
NEA-1746
ZZ-PBMR-400
OECD/NEA PBMR Coupled Neutronics/Thermal Hydraulics Transient Benchmark - The PBMR-400 Core Design (Updated edition)
NEA-1775
ZZ-CLES Cross section library of moderator materials for low-energy neutron sources (New)
NEA-1772
IFPE/IFA-597-MOX Hollow and solid MOX rods experiments (New)
NEA-1697
IFPE/HATAC Fission Gas Release at High Burn-up, Effect of a Power Cycling (Updated edition)
NEA-1424
ZZ FSXLIBJ33 MCNP nuclear data library based on JENDL-3.3 (Updated edition)
NEA-1688
SACALC_CYL Calculates the average solid angle subtended by a volume (New)
NEA-1771
BULK_C-12 Neutron and photon effective dose rates from medium energy protons
or carbon ions through concrete or concrete/iron (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 2006 edition of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) has been released in September. It contains now experimental data for 3955 critical configurations.

  • The International Fuel Performance Experiments Database (IFPE) contains 1183 cases (6 June 2006). Since then new experiments were released in pareticular relative to MOX fuels which are in process of being compiled and evaluated. They shall be integrated into IFPE during 2007.

  • The Shielding Benchmark Experiments Database (SINBAD) includes 41 Reactor Shielding, 27 Fusion Neutronics Shielding, and 15 Accelerator Shielding Experiments (last update: 15 December 2006). The latest additions are the three NAIADE (Graphite, Iron and Water) experiments released by CEA France.  Experiments on photon emission spectra and several experiments related to accelerators, e.g. from the CERF facility are being compiled at present and shall be integrated into SINBAD during 2007.


  • The first edition of the  International Handbook of Evaluated Reactor Physics Benchmark Experiments Handbook (IRPhE) was published in March 2006 and contains reactor physics benchmark specifications that have been derived from experiments that were performed at various nuclear experimental facilities around the world. A Technical Review Committee discussed at the end of October a series of new experiments, it carried out further evaluation work that will be included  in the second edition of the Handbook scheduled for March 2007. A description of the principles and methods used in the production of the Handbook are provided in the summary of this meeting.

  • 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. Additional experimental data from the OECD/NEA Melt Coolability and Concrete Interaction (MCCI) Project have been released and will be available to authorised users in 2007.

Workshops, training courses & tutorials planned for 2007:

  • Schools / Courses / Workshops
    •   2007
      • 22 January - 9 February 2007
        Seminar and Training on Scaling, Uncertainty and 3D Coupled Code Calculations in Nuclear Technology, (3D.S.UNCOP-2007)
        , Department of Nuclear Engineering of Texas A&M, College Station, Texas, USA


      • 12-16 March 2007
        MCNP5 Introductory Class, with additional topics in advanced geometry & criticality
        , University of Pisa, Italy - Programme of Training Course - (Information on accommodation and transportation).


      • Further announcements for possible courses on SCALE5, TRIPOLI-4 and others will be made later. Future courses, tutorials etc. will be held depending on user interest and participation.

    • Courses / Workshops held in 2006
      • 28-29 November 2006
        Journées "codes de calcul en radioprotection, radiophyisque et dosimétrie", INSTN, Saclay
      • 20 November 2006
        NJOY users group meeting, NEA Headquarters, Issy-les-Moulineaux, France (Link contains Proceedings)
      • 15-17 November 2006
        Training Course on Montecarlo Simulation, Universidad Internacional de Andalucía, Baeza (Jaén), Spain
      • 15-17 September 2006
        Workshop on Use of Monte Carlo Techniques for Design and Analysis of Radiation Detectors, University of Coimbra, Coimbra, Portugal
      • 28-31 August 2006
        The OECD Halden Reactor Projects organises every year an International Summer School. The next one is called OECD - HRP Summer School on Water Chemistry of Nuclear Reactor Systems, held at Halden, Norway. The deadline for registration is June 30., (Programme)
      • 23 August - 1 September 2006
        Frédéric Joliot/Otto Hahn Summer School on Nuclear Reactors: Physics, Fuels, and Systems, CEA Cadarache, France
      • 17-21 July 2006
        Intermediate Workshop on MCNPX, ENEA, Bologna, Italy.
      • 4-7 July 2006
        PENELOPE-2006, University of Barcelona, Barcelona, Spain. Scope Objectives and Syllabus.
      • 15-17 May 2006
        TOUGH Symposium 2006, Lawrence Berkeley National Laboratory, Berkeley, California, USA
      • 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)
      • 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

  • Meetings Sponsored by the Nuclear Science Committee & Data Bank

2007

      • 15-19 April 2007
        SNA-2007 + M&C-2007, Joint International Topical Meeting 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
      • 9-13 September 2007
        GLOBAL-2007
        Boise, Idaho, USA
        Contact: Teri Ehresman

2008

      • 13-17 April  2008
        Eleventh International Conference on Radiation Shielding (ICRS11) and Fifteenth Topical on Radiation Protection and Shielding (RPS15). Orhaniser: Georgia Institute of Technology, Callaway Gardens 


      • 25-30 May 2008
        13th International Symposium on Reactor Dosimetry
        Akersloot, Netherlands


2009

      • 3-7 May 2009
        M&C-2009, ANS Mathematics and Computation Division
        Saratoga Springs, NY. USA
        Contact: Tom Sutton


Nuclear Data News:


The JEFF-3.1 Nuclear Data Library is the latest version of the Joint Evaluated Fission and Fusion Library issued by the Data Bank.

The complete JEFF-3.1 Library suite contains:
  • Incident Neutron Data for 381 materials from 1-H-1 to 100-Fm-255
  • Incident Proton Data for 26 materials
  • Radioactive decay data for 3852 isotopes
  • Neutron Induced and Spontaneous Fission Yield Library
  • Activation Library
  • Thermal Scattering Data for 9 materials
The documentation "The JEFF-3.1 Nuclear Data Library", JEFF Report 21, Data Bank, 2006, ISBN 92-64-02314-3, 130 pages was published recently. A limited number of hard copies are available. The corresponding Web page provides further information on the content of the document and the procedure to download the full report.  A CD-ROM with the complete library can also be requested free of charge at the project Web page.

Three ACE format (Monte Carlo) data libraries based on JEFF-3.1 have been released in recent months (see complete list of ACE libraries). Not all contain processed data for all nuclides and materials. Other libraries, based on JEFF-3.1 for deterministic codes are in preparation and will be released during 2007.




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