Data Bank » Data Bank Newsletter

OECD/NEA Data Bank e-newsletter

No. 1, March 2008

Welcome to the first issue of the OECD Nuclear Energy Agency Data Bank's e-newsletter. In order to improve communication with Data Bank users, we aim to publish this newsletter on a regular basis (every two to three months).

OECD Nuclear Energy Agency Data Bank homepage

Contents:
  1. Nuclear data and tools
  2. Processed data libraries
  3. Chemical thermodynamics data
  4. Computer programs
  5. Integral experiments data
  6. Training courses and workshops
  7. Conferences

1. Nuclear data and tools


Nuclear data services cover all aspects of experimental and evaluated nuclear reaction data. This includes: compiling experimental data (EXFOR) and bibliographic information (CINDA); collecting evaluated data (EVA); distributing nuclear data to users; exchanging data with other nuclear data centres; and developing computer software for managing and disseminating nuclear data. These services also include the production, distribution and testing of the Joint Evaluated Fission and Fusion (JEFF) library. For more information visit the nuclear data web page at www.oecd-nea.org/dbdata.

A new release of the nuclear data display program JANIS (version 3.0.1) is available at www.oecd-nea.org/janis/.

Thanks to user feedback, the following improvements and corrections have been implemented:

  • Results from user-specified calculations ('computation' tool in plot window) can now be viewed as tables.
  • EXFOR coverage and exactness have been improved.
  • Some details related to reading the ENDF file 6 (MF=6, differential energy-angle data) have been corrected.

See www.oecd-nea.org/janis/versions.html for more details about the latest changes. To launch the latest release, visit www.oecd-nea.org/janis/webstart/janis.jnlp.

2. Processed data libraries

Recently acquired or tested application data libraries:

  • NEA-1801/01 ZZ VITJEFF31.BOLIB,JEFF-3.1 multi-group coupled (199n + 42gamma) cross-section library in AMPX format for nuclear fission applications.
  • IAEA0867/05 ZZ IRDF-2002-ACE, cross-section library and spectra for dosimetry calculation in ACE format for Monte Carlo methods.
  • DLC-0224/01 ZZ ALBEDO-DATA, data for the calculation of Albedos from concrete, iron, lead and water for photons and neutrons.
  • IAEA1420/01 ZZ ADS-LIB/V1.0, test library for accelerator-driven systems.
  • IAEA1413/01 PGAA-IAEA, database for prompt gamma ray neutron activation analysis.

For additional information on processing nuclear data (tools, libraries, workshops) please visit our website www.oecd-nea.org/dbdata/process/.

3. Chemical thermodynamics data

The fourth phase of the TDB project (TDB-IV) began on 1 February 2008. The TDB project management boards of Phase III met on 19 February 2008 and Phase IV met on 20 February 2008 at the NEA offices. An agreement was reached and as a result, the third phase will be closed; the remaining tasks and budget will be transferred to the fourth phase. The outstanding tasks include completing and publishing the reviews of chemical thermodynamic data for inorganic compounds and complexes of thorium (Th), iron (Fe), and tin (Sn). The fourth phase of the project will comprise:

  • complementary studies of inorganic species and compounds of iron (Fe);
  • a review of auxiliary data;
  • an update of the selected value database accrued during the first three phases of the project;
  • a review of inorganic species and compounds of molybdenum (Mo).

The TDB database can be downloaded from the NEA website by registered users. To register, visit www.oecd-nea.org/dbtdb/utilities/howtoaccess.html.

For more information on the TDB project visit www.oecd-nea.org/dbtdb/.

A database for radiochemical modelling has been acquired recently and the abstract is available at NEA-1210/19 ZZ HATCHES-18.

4. Computer programs

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

  • NEA-1683/01 ERANOS 2.0, modular code and data system for fast reactor neutronics analyses (new).
  • PSR-0352/05 SCAMPI, problem dependent library pre-processing in AMPX format (new version).
  • CCC-0732/03 SCALE 5.1/ORIGEN-ARP5.1: modular system for criticality, shielding, source term, fuel depletion/decay, reactor physics (new version).
  • NEA-1716/04 TRIPOLI-4.4, coupled neutron, photon, electron, positron 3-D, time-dependent Monte Carlo, transport calculation (new).
  • NEA-1564/10/11 EASY-2005.1, European neutron activation system (new).
  • NEA-1800/01 CAFDATS, converter of angular fluxes of DORT, ANISN and TORT systems (new).
  • CCC-0601/06 GENII-LIN-2.1, multi-purpose health physics code (new version).
  • ESTS1678/01 MCSLTT, Monte Carlo simulation of light transport in tissue (tested).
  • NEA-1200/02 ELEORBIT, 3-D simulation of electron orbits in magnetic multi-pole plasma source (tested).
  • CCC-0684/06 NRCDose 2.3.9, evaluation of routine radioactive effluents from nuclear power plants (new version).
  • IAEA1385/01/02/03 CITOPP,CITMOD,CITWI, processing codes for CITATION code (tested).
  • PSR-0541/01 KENO2MCNP, Version 5L, conversion of input data between KENOV.a and MCNP file formats (new).
  • NEA-1755/01 SCIP, radioactive surface contamination investigation program (tested).
  • NEA-1737/02 TALYS-1.0, computes nuclear reactions cross-sections, yields and spectra via a comprehensive set of nuclear models (new).
  • NEA-1628/03 SUSD3D, 1-, 2-, 3-dimensional cross-section sensitivity and uncertainty code (updated release).
  • NEA-1735/05 CARL 2.3, radiotoxicity, activity, dose and decay power calculations for spent fuel (new version).
For more details see the daily updated list at www.oecd-nea.org/tools/abstract/new.

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

5. Integral experiments data

    Fuel behaviour
      The International Fuel Performance Experiments (IFPE) Database was recently updated and now includes:

      • NEA-1799/01 IFPE/AEKI-EDB-E110, experimental database of E110 claddings under accident conditions (restricted access);
      • NEA-1803/01 IFPE/IFA-585, in-reactor creep behaviour of zircaloy-2 and zircaloy-4 under variable loading conditions (restricted access).

    Reactor physics

    Experimental data in support of nuclear safety
      A steam explosion experiments (STEX) database is in preparation. The University of Wisconsin and the NEA Nuclear Safety Division are working together on this project.

6. Training courses and workshops

  • 7-11 April 2008
    A training course on the Monte Carlo computer code TRIPOLI-4 will be held at the OECD/NEA offices. TRIPOLI-4 Course Programmme. Registration closed.

  • 12-16 May 2008
    Joint introductory/intermediate MCNP/MCNPX training course, ITN, Sacavem, Lisbon (Portugal) - co-sponsored by ORNL/RSICC. Registration closed.

  • 19-23 May 2008
    GEANT4 (a toolkit for the simulation of the passage of particles through matter) workshop organised at ORNL by the Radiation Shielding Information Computational Center (RSICC) in co-operation with the NEA Data Bank.


  • 30 June - 3 July 2008
    Training course on PENELOPE 2008 - a code system for Monte Carlo simulation of electron and photon transport. Scope and objectives, syllabus and accommodation. Registration closed.

  • 1-12 September 2008
    The training course on experiment, theory and evaluation of nuclear data (EXTEND) for young professionals is to be held in Budapest, Hungary.

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

  • 13 -17 October 2008
    Sensitivity and Uncertainty Analysis Training Course using SCALE TSUNAMI, held at KFKI Budapest, Hungary. Syllabus. Registration Form.
  • 27 - 31 October 2008
    Joint introductory/intermediate MCNP/MCNPX training course, GRS, Garching near Munich (Germany) - co-sponsored by ORNL/RSICC.  Registration form.
  • 16 - 20 March 2009
    Training course on "Analytical Benchmarks: Case Studies in Neutron Transport Theory" using the Handbook (including computer codes) 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. Teacher: Prof. Barry D. Ganapol.
  • 23 - 27 March 2009
    MCNP6 Training course, OECD/NEA

7. Conferences


Meetings and conferences sponsored by the OECD/NEA Nuclear Science Committee and Data Bank

See also: Other NEA nuclear science meetings

To access the latest issue of the NEA monthly electronic bulletin, visit www.oecd-nea.org/new.html.