OECD/NEA Data Bank E-Newsletter

No. 2, July 2008

The 17th Meeting of the Executive Group of the Nuclear Science Committee (Data Bank Management Committee) was held from 24 to 25 June 2008, chaired by Pierre D’hondt and attended by 23 delegates from participating countries. The Data Bank activities and its budgets relative to 2007 and 2008 as well as planned activities and budgets for 2009 and 2010 were discussed and approved.
Like in the previous year, also this year’s meeting was prolonged by a half day to discuss a questionnaire on “evolution of the Data Bank to meet future challenges”, which is a continuation of last year’s discussion session on “the future of the Data Bank”. Also a special session on “new generation of computer codes in nuclear engineering” was held where three invited guest speakers from US, France and Japan have shared their common understanding on what is happening in the world of computer codes for nuclear science and technology and how they are expected to evolve in the future. A Workshop on this topic will be prepared for 2009.

On new generation of computer codes in nuclear engineering:

  1. Nuclear data and tools
  2. Processed data libraries
  3. Chemical thermodynamics data
  4. Computer programs
  5. Integral experiments data
  6. Benchmarks
  7. Training courses and workshops
  8. Conferences
  9. Other items

1. Nuclear data and tools

The following nuclear data libraries have recently been added to the evaluated nuclear data (EVA) database:

The EVA database contains a large number of evaluated data libraries, all in ENDF format; it can be consulted at www.oecd-nea.org/dbdata/eva/evaret.cgi. More information on evaluated data libraries is available at www.oecd-nea.org/dbdata/data/nds_eval_libs.htm.
Participants in the Joint European Fission and Fusion (JEFF) nuclear data evaluation project met on 21-23 May 2008 in Aix-en-Provence, France. Meeting participants reviewed feedback from the verification and validation of the current version of the JEFF data library and discussed evaluations to be incorporated into a future release of the library. A new release of JEFF-3.1.1/RDD, the radioactive decay data library, is now available on CD-ROM. The full documentation for the radioactive decay data library is currently being prepared for publication. More information is available at www.oecd-nea.org/dbdata/projects/nds_jef.htm.

2. Processed data libraries

Recently acquired or tested application data libraries:

For a full list of processed cross-section data libraries visit www.oecd-nea.org/dbprog/categ-z.html.

The most recent updates to NJOY, a data processing system of evaluated nuclear data files in ENDF format, visit www.oecd-nea.org/dbprog/njoy-links.html.

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

3. Chemical thermodynamics data

A new review will appear soon. The Thorium review has gone to press.
The two reviews selected for from Phase IV of the TDB project are:

The TDB database can be downloaded from the NEA website by registered users. To register, please visit www.oecd-nea.org/dbtdb/utilities/howtoaccess.html
More information on the TDB project is available at www.oecd-nea.org/dbtdb/.

4. Computer Programs

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

For more details see the daily updated list at www.oecd-nea.org/dbprog/cpsnew.html.

5. Integral experiments data

Fuel behaviour
The International Fuel Performance Experiments (IFPE) Database was recently updated and now includes:
  • NEA-1809/01 IFPE/STEED-I Stored Energy / Enthalpy Determination from Studsvik 
  • NEA-1722/01 IFPE/ROPE-I, BWR, 4 rods, Ringhals, investigates clad creep-out from Studsvik (1986-1993)
  • NEA-1723/01 IFPE/ROPE-II, PWR rod over pressure experiment from Studsvik
  • NEA-1806/01 IFPE/DEFEX, Studsvik DEFEX BWR fuel secondary defect formation as a consequence of primary defects
  • NEA-1807/01 IFPE/DEFEX-II DEMO, BWR fuel primary defect and conditions leading to secondary failure of the cladding by hydriding
  • NEA-1788/01 IFPE/BN-MOX-M109/D3, Belgonucleaire Beznau-1 PWR irradiated MOX Fuel Rod M109/D3
  • NEA-1812/01 FUELPERFORMANCE-REP, Seminars on nuclear fuel performance based on basic underlining phenomena, proceedings
  • Reactor physics
    The March 2008 edition of the International Reactor Physics Benchmark Experiments (IRPHE) Project handbook is now available at www.oecd-nea.org/dbprog/IRPhE-latest.htm.
    The next IRPhE review meeting preparing the 2009 edition of the IRPhE Handbook is scheduled for October 2008.

    Legacy Handbook by N. M. Schaeffer:
    NEA-1814/01 REACTORSHIELDING-NMS, Reactor Shielding for Nuclear Engineers.

    6. Benchmarks

    7. Training courses and workshops

    8. Conferences

    Meetings and conferences Sponsored by the Nuclear Science Committee & Data Bank

    9. Other items

    Information on joint research projects related to nuclear safety
    A steam explosion experiments (STEX) database is now ready (International Steam Explosion Experimental Data Base). The University of Wisconsin and the NEA Nuclear Safety Division are working together on this project.