OECD/NEA Data Bank

Computer Program Service (CPS) E-Newsletter

No. 15, September 2003

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

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


Identification Name Description
NEA-1688 SACALC2 Calculates the average solid angle for source-detector geometries (New)
NEA-1708 ADEFTA 1.0 Atomic Densities for Transport Analysis (New)
IAEA1405 CHAINFINDER 2.16 search for transmutation chains under neutron irradiation (New)
IAEA1384 NKE 2.16 Nuclide Explorer tool for retrieving interactively detailed data on radionuclides properties (New)
IAEA1404 CHAINSOLVER 2.20 transmutation simulation of samples during irradiation in nuclear reactors (New)
IAEA1169 EMPIRE-II 2.18 Comprehensive Nuclear Model Code, Nucleons, Ions Induced Cross-Sections (Updated)
NEA-1694 SATIF/CYCLO-RADSAFE Health Physics and Radiological Safety of Cyclotrons 10-250 MeV (New)
NEA-1424 ZZ FSXLIBJ33 MCNP nuclear data library based on JENDL-3.3 (New)
NEA-1707 ZZ-MATXSLIBJ33 JENDL-3.3 based, 175 N-42 photon groups (VITAMIN-J) MATXS library for discrete ordinates multi-group (New)
NEA-1560 IFPE/BR3-HBFRHCP BR-3 High Burnup Fuel Rod Hot Cell Program (New)
NEA-1599 IFPE/FUMEX-I Data from OECD Halden Reactor Project for FUMEX-1 (Fuel Modelling at Extended Burnup) (New)
NEA-1627 BOT3P2.0 2D/3D Mesh Generator and Graphical Display of Geometry and Results for Deterministic Transport Codes (New)
NEA-1678 BOT3P3.0 3D Mesh Generator and Graphical Display of Geometry for Radiation Transport Codes, Display of Results (New)
PSR-0242 SABRINA Geometry Plot Program for MCNP (New, Linux version)
IAEA1365 ZZ-RIPL-2 Parameter Library for Nuclear Model Calculations (New)
NEA-1603 DCHAIN-SP 2001 Code System for Analyzing Decay and Build-up Characteristics of Spallation Products (Updated)
IAEA1401 ZZ-DROSG-2000 Legendre Coefficient Library for 59 monoenergetic neutron source reactions (New)
IAEA1402 ENDVER The ENDF File Verification Support Package (New)
IAEA0848 RECENT2002 Reconstruction of Cross Sections Data from Resonance Parameters (New)
IAEA1314 RELABEL2002 Labels FORTRAN Statements in ENDF Format Processing Programs (New)
IAEA0854 SIGMA1-2002 Doppler Broadening ENDF Format Linear-Linear. Interpolated Point Cross Section (New)
IAEA1283 SIXPAK2002 ENDF Format Double Differential Cross Section Converter to Single Differential Format (New)
IAEA1380 ACTIVATE2002 Activation Cross Section by Combining Cross Section and Multiplier (ENDF Fomat) (New)
IAEA0932 VIRGIN2002 Calculates Uncollided Neutron Flux and Neutron Reactions from Transmission in ENDF Format (New)
NEA-1564 EASY-2001 European Neutron Activation System (New)
IAEA1379 PREPRO2002 Data Preparation and Management, Subsidiary Calculations (ENDF Format) (New)
IAEA1321 COMPLOT2002 Compare ENDF/B Plots of Reaction Data (New)
IAEA1307 CONVERT2002 FORTRAN Program Converter for Different Computers (New)
IAEA1308 DICTIN2002 Reaction Index Generated for ENDF Format (New)
IAEA1309 FIXUP2002 ENDF Format Redundant Cross-Sections Check (New)
IAEA1310 LEGEND2002 Angular Distribution Table Calculations in ENDF Format (New)
IAEA1312 MERGER2002 Merges ENDF/B Data by Material Number or Identifier (New)
IAEA1313 MIXER2002 Cross Sections Calculations for a Composite Mixture of ENDF Format Material (New)
IAEA1311 LINEAR2002 Linear-Linear Interpolation of ENDF Format Cross-Sections (New)
IAEA0849 GROUPIE2002 Bondarenko Self-Shielded Cross Sections from ENDF/B (New)
IAEA1322 EVALPLOT2002 ENDF Plots Cross Section, Angular Distribution and Energy Distribution(New)
NEA-1525 PENELOPE2003 A Code System for Monte-Carlo Simulation of Electron and Photon Transport (New)
NEA-1706 MMRW Canadian and early British Energy Reports on Nuclear Reactor Theory (1940-1946) (New)
PSR-0365 MOCUP MCNP/ORIGEN Coupling Utility Programs (New)
NEA-1492 NUCLEUS-CHART Interactive Chart of Nuclides (New)
NEA-1517 SINBAD-BALAKOVO-3 VVER-1000 Ex-vessel Neutron Dosimetry Benchmark (New)
NEA-0446 DELIGHT-7 Point Reactivity Burnup for HTGR Lattice with P1 Neutron Scattering Approximation (Tested)
NEA-1671 DUCT-III Design Code for Duct-Streaming Radiations (Tested)
NEA-1663 PLUTON Isotope Generation and Depletion in Highly Irradiated LWR Fuel Rods (Tested)
IAEA1403 C-SHIELDER Gamma shielding calculations of radionuclides emitting photons 0.5 to 10 MeV by different concretes (Tested)
NEA-1086 TRISTAN 3-D fixed source radiation transport (Tested)

Note: All computer codes with documentation documentation are now distributed exclusively in electronic form either on  CD-ROM or via FTP. No paper copies of manuals are provided.

For more details see weekly updated list(on Mondays)

Integral Experiments Data for Model and Code Validation

Compilations and evaluations have been updated concerning the:
  • Shielding Experiments Data Base (SINBAD) at NEADB or RSICC
  • Work is in progress on the International Reactor Physics Benchmark Experiments Project. See IRPhE.
  • The International Fuel Performance Experiments Database (IFPE) was recently enriched with new experiments.

Workshops, Training Courses & Tutorials completed in 2003:

  • 2nd International Workshop on 'Advanced radiation transport simulation with PENELOPE (electron-photon transport)', held in Salou (Tarragona) from 8-10 January 2003.(Penelope User Group meeting)
  • MCNP5 Intermediate/Advanced Level Training Course, 24-28 March 2003, at the Imperial College, London, England 
  • KENO / SCALE Training Courses 2003, 23-27 June 2003 in Paris France
  • TOUGH Symposium , Lawrence Berkeley National Laboratory (LBNL), 15-17 May, A symposium on applications and enhancements of  TOUGH (A General-Purpose Numerical Simulator for Multiphase Fluid and Heat Flow) with oral and poster presentations. Proceedings on CD-ROM will be available at the Symposium. 

  • Contact: Stefan Finsterle, George J. Moridis, Curtis M. Oldenburg, Yu-Shu Wu LBL, E-mail: SAFinsterle@lbl.gov
  • PENELOPE-2003 (electron-photon transport) training course / tutorial, (7-10 July 2003, NEA, Paris), (see previous workshop report)
  • QUADOS workshop: Intercomparison on the Usage of Computational Codes in Radiation Dosimetry,   14 - 16 July  2003, Bologna, Italy, organised by: ENEA and University of Bologna, co-sponsored by: EURADOS, OECD/NEA, Contact: Gianfranco Gualdrini guald@bologna.enea.it 
  • The 2003 Frederic Joliot & Otto Hahn Summer School in Reactor Physics: Modern Reactor Physics and the Modelling of Complex Systems held at the Forschungszentrum Karlsruhe/Ftu,  Hermann-Von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen, Germany from 20 - 29  August 2003
  • MCNP5 Introductory Training Course, 15-19 September 2003 Issy-les-Moulineaux (France) 
  • Workshop on Common Tools and Interfaces for Deterministic Radiation Transport, for Monte Carlo and Hybrid Codes ( 25-26 September 2003). Participants will receive a copy of the proceedings containing the presentations and a summary on CD-ROM.

Workshops, Training Courses & Tutorials planned for 2003: 

Future courses, tutorials etc. will be held depending on user interest and participation.

Meetings Sponsored by the Nuclear Science Committee & Data Bank

Meetings scheduled for the next two years and of interest to clients of the Computer Program Service 

In particular we signal here:

News from the OECD Nuclear Energy Agency (NEA)

The latest issue of the NEA on-line bulletin.