OECD/NEA Data Bank

Computer Program Service (CPS) E-Newsletter

No. 25, September 2005 

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. Results of polling on the use of computer codes 

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

 
Identification Name Description
NEA-1747/01
MONTE-CARLO-WS-2005
Proceedings of Monte Carlo Criticality Calculations & TRIPOLI-IV Workshops 2005
IAEA0867/04 ZZ IRDF-2002 640-Group Cross-Section Library and Spectra for Dosimetry Calculation in ENDF-6 Format (New)
USCD1232/01 ODEPACK Initial Value Problems of Ordinary Differential Equation System (New)
USCD1227/01
LSODA Ordinary Differential Equation Solver for Stiff or Non-Stiff System (New)
USCD1228/01
LSODAR Ordinary Differential Equation Solver for Stiff or Non-Stiff System with Rootfinding (New)
USCD1224/01
LSODI Implicit Ordinary Differential Equations System Either Dense or Banded Matrices (New)
USCD1225/01
LSODIS Implicit Ordinary Differential Equations System Sparse Matrices (New)
USCD1229/01
LSODES Ordinary Differential Equations System Sparse Matrices (New)
USCD1223/01
LSODE 1st Order Stiff or Non-Stiff Ordinary Differential Equations System Initial Value Problems (New)
USCD1230/01
LSODKR Stiff Ordinary Differential Equations (ODE) System Solver with Krylov Iteration with Rootfinding (New)
USCD1226/01
LSOIBT Implicit Ordinary Differential Equations System Block Tridiagonal Matrices (New)
USCD1231/01
LSODPK Ordinary Differential Equations Solver for Stiff and Nonstiff System with Krylov Corrector Iteration (New)
IAEA1412/02
ZZ-MINSKACT Evaluated neutron reaction data for Th-232, Pa, U, Np, Pu, Am and Cm isotopes (New)
NEA-1746/01
ZZ-PBMR-400 OECD/NEA PBMR Coupled Neutronics/Thermal Hydraulics Transient Benchmark - The PBMR-400 Core Design (New)
IAEA1395/05
XNWLUP3.0 Graphical user interface to plot WIMS-D library multigroup cross sections (Revised Edition)
NEA-1735/03
CARL2.1 radiotoxicity, activity, dose and decay power calculations for spent fuel (Revised Edition)
NEA-1552/19
SINBAD-TEPC-FLUKA
TEPC-FLUKA Comparison (New)
NEA-1517/72
SINBAD-RFNC-PHOTONS
Photon Leakage Spectra from Al, Ti, Fe, Cu, Zr, Pb, U238 Spheres (New)
NEA-1525/10
PENELOPE2005
A Code System for Monte-Carlo Simulation of Electron and Photon Transport (Tested)
NEA-1640/08
ZZ-BWRTT
BWR Turbine Trip Transient Benchmark Based on Peach-Bottom 2 (Revised Edition)
NEA-1739/01 IRPhE/AVR
High Temperature Reactor Experience, Archival Documentation (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) was updated with new experiments and contains now 851 cases (1 June 2005).
  • The Shielding Benchmark Experiments Database (SINBAD) includes now 36 Reactor Shielding-26 Fusion Neutronics Shielding-, and 13 Accelerator Shielding-Experiments. (last update: 27 September 2005). A new version will be issued 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 and 2006:

  • Courses / Workshops
    • For 2005
      • Workshop on Evaluation of Uncertainties in Relation to Severe Accidents and Level 2 Probabilistic Safety Analysis, Cadarache (France), 7-9 November 2005


    •  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
      • 15-17 September 2006
        Workshop on Use of Monte Carlo Techniques for Design and Analysis of Radiation Detectors, University of Coimbra, Coimbra, Portugal
      • 25-29 September 2006
        9th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation
        Nimes, Frances
    • 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 (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, 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

  • Meetings Sponsored by the Nuclear Science Committee & Data Bank
      2005
    • Meetings scheduled

      • 2-6 October 2005
        Nureth 11 - Nuclear Reactors Thermal-Hydraulics
        Avignon
        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

      • 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
        http://accapp05.infm.it/

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

        Avignon, Palais des Papes, France
        http://mcavignon2005.cea.fr/

      • 18-22 September 2005
        2005 Nuclear Criticality Safety Topical - Integrating Criticality Safety into the Resurgence of Nuclear Power

        Knoxville, TN, USA
        http://meetingsandconferences.com/ncsd2005/

      • 19-23 September 2005
        Sixth International Conference on WWER Fuel Performance, Modelling and Experimental Support

        Albena, Bulgaria

2006

      • 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
        http://www.ans-rpsw-carlsbad.com

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

        Chair: Hee-seock LEE
        Pohang Accelerator Laboratory POSTECH, Korea, Rep.
        http://www.oecd-nea.org/html/science/meetings/SATIF-8/satif8.html

      • 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

    2007

      • 15-18 April 2007
        SNA-2007 + M&C-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

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