OECD/NEA Data Bank

Computer Program Service (CPS) E-Newsletter

No. 32, February 2007


The co-operative arrangement between US-DOE and the OECD/NEA concerning the exchange of computer codes and nuclear data has now been implemented both at the Radiation Shielding Information Computational Center (RSICC) and the NEA Data Bank. The computer codes and associated data libraries released by RSICC will once again be distributed by the NEA Data Bank.

We all look forward to a renewed and strong co-operation with RSICC.


Starting March 2007, we have been asked to identify end-users of the packages we distribute (the end-user is the person who will be using the software in your establishment). We also need a statement on the applications/reasons for which this information will be used. From now on, requesters must provide this information at the time they place the request.

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
Computer Codes and associated Data Libraries
SACALC_CYL Calculates the average solid angle subtended by a volume (Tested)
IAEA1388/05 FOTELP-2K6 Photons, Electrons and Positrons Transport in 3D by Monte Carlo Techniques (New Version)
NEA-1561/10 CHEMENGL/CHIMISTE Chemical and Physical Properties of Elements (New Version)
CCC-0730/01 MCNP/MCNPX Monte Carlo Particle Transport Code System Including MCNP5 1.40, MCNPX 2.5.0, VISED19L and Data Libraries (New)
CCC-0732/01 SCALE5.1/ORIGEN Modular system for criticality, shielding, source term, fuel depletion/decay, reactor physics (New)
CCC-0707/02 PARTISN 4.0 1-D, 2-D, 3-D Time-Dependent, Multigroup Deterministic Parallel Neutral Particle Transport Code (New)
CCC-0638/09 TART2005 3D Coupled N-Photon Combinatorial Geometry Time Dependent Monte Carlo Transport Code (New)
CCC-0721/01 GRTUNCL3D Code to Calculate Semi Analytic First Collision Source and Uncollided Flux (X, Y, Z) (New)
PSR-0534/01 PUFF-IV Code System to Generate Multigroup Covariance Matrices from ENDF/B-VI Uncertain­ty Files (New)
NEA-1678/08 BOT3P5.2 3D Mesh Generator and Graphical Display of Geometry for Radiation Transport Codes, Display of Results (New Version)
NEA-1708/04 ADEFTA 3.1 Atomic Densities for Transport Analysis (New Version)
NEA-1779/01 SAGEP-FR Sensitivity Analysis of Fast Reactor Parameters (New)
Coupled Channel, Statistical Model, Schroedinger and Dirac Equation, Dispersion Relation (New Version)
Integral Experiments Data
CSNI2008/01 MASCA In-vessel phenomena during severe accidents (New) (Restricted Distribution)
CSNI2003/01 MCCI PROJECT Molten Core Concrete Interaction Project (New) (Restricted Distribution)
IFPE/NOVOVORONEZH-R1 operation factor data of the Novovoronezh VVER-1000 fuel assembly 4108 rods (Updated Edition)
IFPE/FMDP-MOX4-5 Weapons-Derived MOX Fuel DOE FMDP Test Irradiations Capsules 4 & 5, Advanced Test Reactor (ATR) (New)
IFPE/IFA-508 & 515 PCMI Behaviour of Thin Cladding Rods, JAERI and HRP (New Archive)
IFPE/GBGI Grain-Bubble Gas Interlinkage (New Archive)
NEA-1780/01 PWR-MOX/UOX-TRANS OECD/NEA US-NRC PWR MOX/UO2 Core Transient Benchmark (New)

For more details see daily updated list

  • List of the programs by subject field
  • Graphs with statistical service data for 2006

Poll: In view of adapting our service to changing technologies we are carrying out a poll with our users to verify, whether or not they can read DVDs. Please provide here your answer to our query.

Integral Experiments Data for Model and Code Validation:

  • 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 1187 cases (6 March 2007). Since then new experiments were released in particular 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: 5 January 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. The next edition will be issued in March 2007.

  • 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 and the OECD/NEA MASCA Project have been released and are available to authorised users.

Workshops, training courses & tutorials planned for 2007:

  • Schools / Courses / Workshops
    •   2007

      • 7 May 2007
        Introduction to MCNP using the Visual Editor in Richland, Washington, USA.
      •  16 July 2007
        Advanced class on the Visual Editor, CAD to MCNP conversion and data Visualization using Excel,
        Please contact Randy Schwarz for more information: randyschwarz@mcnpvised.com or http://www.mcnpvised.com
      • Further announcements for possible courses on SCALE5, TRIPOLI-4, MCNP/MCNPX, PENELOPE and others will be made later. Future courses, tutorials etc. will be held depending on user interest and participation.

    • Courses / Workshops held in 2006 and 2007
      • 12-16 March 2007
        MCNP5 Introductory Class, with additional topics in advanced geometry & criticality, University of Pisa, Italy, OECD NEA Data Bank - co-sponsored by ORNL/RSICC (Information on accommodation and transportation). (Registration closed now)
      • 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
      • 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


      • 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
        Boise, Idaho, USA
        Contact: Teri Ehresman


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

      • 21-23 April 2009
        SATIF-9, Shielding Aspects of Accelerators, Targets and Irradiation Facilities -
        Spallation Neutron Source, SNS, 701 Scarboro Road, OAK RIDGE, TN, USA
      • 25-30 May 2008
        13th International Symposium on Reactor Dosimetry
        Akersloot, Netherlands


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

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