OECD/NEA Data Bank

Computer Program Service (CPS) E-Newsletter

No. 35, December 2007

Reminder: Requests for computer codes acquired from RSICC under the new co-operative arrangement (signed on 10 April, 2006) have to undergo an additional screening procedure. End-users need to fill in FORMS in order to obtain a single user/single site license for using such codes. If you have already downloaded these forms, please note that the instructions have been updated.

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
NEA-1209/08 DWBA07/DWBB07 Elastic scattering with nucleon-nucleon potential and DWBA for inelastic scattering (New Version)
ESTS1365/01 NLCGCS_MPV3.0 Inversion of electromagnetic fields for subsurface electrical properties (New)
ESTS0608/01 RSAC-6 Gamma doses, inhalation and ingestion doses, fission products inventory after fission products release (New)
CCC-0729/01 SERA-1C0 Simulation environment for radiotherapy applications (New)
PSR-0482/01 REMIT 5.1 Radiation exposure monitoring and information transmittal system (New)
PSR-0523/01 DEPLETOR V.2 Provides depletion capability to the Purdue Advanced Reactor Core Simulator (PARCS) code (New)
PSR-0533/01 SQUIRT 1.1 Predicts leakage rate and crack area for cracked pipes in nuclear power plants (New)
CCC-0601/06 GENII-LIN-2.1 Multipurpose Health Physics Code (Revised Version)
IAEA1379/04 PREPRO2007 Data Preparation and Management, Subsidiary Calculations (ENDF Format) (New Version)
IAEA0849/15 GROUPIE2007 Bondarenko Self-Shielded Cross Sections from ENDF/B (New Version)
IAEA1310/11 LEGEND2007 Angular Distribution Table Calculations in ENDF Format (New Version)
IAEA1311/15 LINEAR2007 Linear-Linear Interpolation of ENDF Format Cross-Sections (New Version)
IAEA1312/14 MERGER2007 Merges ENDF/B Data by Material Number or Identifier (New Version)
IAEA0848/17 RECENT2007 Reconstruction of Cross Sections Data from Resonance Parameters (New Version)
IAEA1314/10 RELABEL2007 Labels FORTRAN Statements in ENDF Format Processing Programs (New Version)
IAEA0854/15 SIGMA1-2007 Doppler Broadening ENDF Format Linear-Linear. Interpolated Point Cross Section (New Version)
IAEA1283/06 SIXPAK2007 ENDF Format Double Differential Cross Section Converter to Single Differential Format (New Version)
IAEA0932/10 VIRGIN2007 Calculates Uncollided Neutron Flux and Neutron Reactions from Transmission in ENDF Format (New Version)
IAEA1380/04 ACTIVATE2007 Activation Cross Section by Combining Cross Section and Multiplier (ENDF Fomat) (New Version)
IAEA1321/13 COMPLOT2007 Compare ENDF/B Plots of Reaction Data (New Version)
IAEA1307/14 CONVERT2007 FORTRAN Program Converter for Different Computers (New Version)
IAEA1308/12 DICTIN2007 Reaction Index Generated for ENDF Format (New Version)
IAEA1322/16 EVALPLOT2007 ENDF Plots Cross Section, Angular Distribution and Energy Distribution (New Version)
IAEA1309/11 FIXUP2007 ENDF Format Redundant Cross-Sections Check (New Version)
IAEA1313/11 MIXER2007 Cross Sections Calculations for a Composite Mixture of ENDF Format Material (New Version)
USCD1235/01 ENDF-UTILITY-CODES Codes to check and standardize data in the Evaluated Nuclear Data File (ENDF) (New)
USCD1208/07 CHECKR-7.01 ENDF/B Format Check (New Version)
USCD1209/07 FIZCON-7.02 ENDF/B Cross-Sections Redundancy Check (New Version)
USCD1216/07 PSYCHE-7.02 ENDF/B Data Consistency Check in ENDF Format (New Version)
USCD1212/07 INTER-7.01 ENDF/B Thermal Cross-Sections, Resonance Integrals, G-Factors Calculation (New Version)
USCD1218/07 STANEF-7.01 ENDF/B Book-keeping Operations for ENDF Format Files (New Version)
NEA-0914/07 REFIT-2007 Multilevel Resonance Parameter Least Square Fit of Neutron Transmission and Capture Data (Now Tested)
USCD1236/01 ZZ-SCALE5.1/COVA-44G 44-group cross section covariance matrix library extracted from SCALE5.1 (New)
NEA-1730/03 ZZ-COV-15GROUP-2006 15-group cross section covariance matrix library (New)
NEA-1798/01 ANGELO-LAMBDA Covariance matrix interpolation and mathematical verification (New)
Integral Experiments Data
NEA-1769/02 ZZ-UAM-LWR Uncertainty Analysis in Modelling, Coupled Multi-physics and Multi-scale LWR analysis (New Edition) - Restricted to participants and authors in UAM-2006
NEA-1731/06 ZZ-BFBT OECD/NEA-US/NRC NUPEC BWR Full-size Fine-mesh Bundle Tests Benchmark (New Edition) - Restricted access

For more details see daily updated list

Integral Experiments Data for Model and Code Validation:

  • The 2007 edition of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) has been released in September 2007. It contains now experimental data for over 4092 critical configurations. Access to request a copy.

  • The International Fuel Performance Experiments Database (IFPE) contains 1209 cases (November 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 2008.

  • The Shielding Benchmark Experiments Database (SINBAD) includes 42 Reactor Shielding, 27 Fusion Neutronics Shielding, and 15 Accelerator Shielding Experiments (last update: 21 May 2007).

  • The second edition of the  International Handbook of Evaluated Reactor Physics Benchmark Experiments Handbook (IRPhE) was published in March 2007 and contains reactor physics benchmark specifications that have been derived from experiments that were performed at various nuclear experimental facilities around the world. The third edition, including new evaluations, is scheduled for March 2008.

  • Prof. M.M.R Williams has released the following three of his legacy books for free distribution for use by students and other researchers.

    • The Slowing Down and Thermalization of Neutrons, North-Holland Publishing Company - Amsterdam, 582 pages, 1966
    • Mathematical Methods in Particle Transport Theory, Butterworths, London, 430 pages, 1971
    • Random Processes in Nuclear Reactors, Pergamon Press Oxford New York Toronto Sydney, 243 pages, 1974

  • Prof. Jeffery Lewins has recently released the following two legacy books:
    • Importance: The Adjoint Function : The Physical Basis of Variational and Perturbation Theory in Transport and Diffusion Problems.
    • Nuclear Reactor Kinetics and Control
    • These will be available in the near future on CD-ROM.

    Workshops, training courses & tutorials planned for 2008:

    • 30 January - 1 February 2008
    • Course on "Analytical Benchmarks: Case Studies in Neutron Transport Theory" using the Handbook (including computer codes) to be published on "Analytical Benchmarks for Nuclear Engineering Applications (Case Studies in Neutron Transport Theory)". This course is intended for transport methods developers and those who teach reactor physics and transport theory. In addition, the course would be appropriate for anyone with an analytical interest in solving equations and the application of numerical methods to obtain extreme accuracy (Registration now closed).
      Teacher: Prof. Barry D. Ganapol.

    • 25-29 February 2008 Sensitivity and Uncertainty Analysis Training Course using SCALE TSUNAMI Syllabus, held at OECD/NEA Headquarters. Registration Form.
    • 7-11 April 2008 A training course on the Monte Carlo computer code TRIPOLI-4 will be held  at OECD/NEA Headquarters. TRIPOLI-4 Course Programmme. The new version that is being released contains cross section libraries from the latest evaluations. It contains also an interactive pre-processor for preparing of geometries. Registration Form.
    • 12-16 May 2008
      Joint introductory/intermediate MCNP/MCNPX training course, ITN, Sacavem, Lisbon (Portugal) - co-sponsored by ORNL/RSICC. Registration form.
    • 19-23 May 2008
      GEANT4 (a toolkit for the simulation of the passage of particles through matter) workshop  organised at ORNL by the RSICC (Radiation Shielding Information Computational Center) in co-operation with the NEA Data Bank. Programmme, schedule and additional information.
    • 2-6 June 2008
      REFIT-2007 Training courseMultilevel Resonance Parameter Least Square Fit of Neutron Transmission and Capture Data, EC-JRC-IRMM, Geel, contact  Peter Schillebeeckx
    • 30 June - 3 July 2008
    • Training course on PENELOPE-2008 - a Code System for Monte Carlo Simulation of Electron and Photon Transport. Scope & Objectives, Syllabus and accommodation. Registration form.

    • 29 September - 3 October 2008
      Training Course on FLUKA, a fully integrated particle physics MonteCarlo simulation package. OECD/NEA Data Bank, Issy les Moulineaux, France. Registration Form.

    • Meetings Sponsored by the Nuclear Science Committee & Data Bank