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
member 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:
- Nuclear data and tools
- Processed data
- Chemical thermodynamics
- Computer programs
- Integral experiments
- Training courses and
- Other items
1. Nuclear data and tools
The following nuclear data libraries
have recently been added to the
evaluated nuclear data (EVA) database:
- UK Heavy Element Decay Data library, UKHEDD-2.6;
- UK Activation Product Decay Data library, UKPADD-6.8.
The EVA database contains a large number of evaluated data
libraries, all in ENDF format; it can be consulted at
www.oecd-nea.org/html/dbdata/eva/evaret.cgi. More information on evaluated
data libraries is available at
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
2. Processed data libraries
Recently acquired or tested
- NEA-1822/01 ZZ FLUKA05-PRE-LIB, FLUKA05 Multi-group, multi-purpose nuclear data
library, neutrons, photons, charged particles.
- NEA-1818/01 ZZ KASHIL-E70, 199 N, 42 Photon Groups Cross Sections in MATXS Format
Based on ENDF/B-VII.0 for Shielding Applications.
- NEA-1817/01 ZZ KAFAX-J33, 150 and 12 Groups Cross Section Library in MATXS Format
based on JENDL-3.3 for Fast Reactors.
- NEA-1816/01 ZZ KAFAX-F31, 150 and 12 Groups Cross Section Library in MATXS Format
based on JEFF-3.1 for Fast Reactors.
- NEA-1815/01 ZZ KAFAX-E70, 150 and 12 Groups Cross Section Library in MATXS Format
based on ENDF/B-VII.0 for Fast Reactors.
For a full list of processed cross-section data
The most recent
updates to NJOY, a data processing system of evaluated nuclear data
files in ENDF format, visit www.oecd-nea.org/html/dbprog/njoy-links.html.
For additional information on processing nuclear data
libraries, workshops, …) please visit our website www.oecd-nea.org/html/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:
- complementary studies of inorganic species and
compounds of iron (Fe),
- a review of auxiliary data
The TDB database can be downloaded from the NEA website
registered users. To register, please visit www.oecd-nea.org/html/dbtdb/utilities/howtoaccess.html
More information on the TDB project is available at www.oecd-nea.org/html/dbtdb/.
4. Computer Programs
The most recently acquired or tested
codes and application data libraries are:
- NEA-1826/01 SOLTRAN, solving multi-dimensional simplified P2 transport and
diffusion problems of hexagonal geometry in fast reactors (New)
- NEA-1825/01 RIMACS, Reactor Inspection Main Control System (New)
- NEA-1824/01 KCUT, code to generate minimal cut sets for fault trees (New)
- NEA-1821/01 IPLOT, interactive MELCOR data plotting system (New)
- NEA-1820/01 GTSP, automatic ultrasonic inspection of Guide Tube Support Pin in nuclear
power plants (New)
- NEA-1819/01 BURD,
Bayesian estimation in data analysis of Probabilistic Safety
- NEA-1813/01 EASYQAD version 1.0, Visualization for Gamma and Neutron Shielding
- NEA-0919/06 SRIM-2008, Stopping Power and Range of Ions in Matter (New version)
- NEA-1708/06 ADEFTA 4.1, Atomic Densities for Transport Analysis (New version)
- CCC-0522/04 VARSKIN-3 V3.0.1, Dose Calculation for Skin Contamination, with Sadde Input Generator (New version)
- CCC-0553/07 RASCAL 3.0.5, Radiological Doses from Accidental Release to Atmosphere (New version)
- CCC-0684/07 NRCDose 2.3.10, Evaluation of Routine Radioactive Effluents from Nuclear Power Plants (New version)
- NEA-1823/01 ICRS1, Proceedings of the First Radiation Shielding Symposium, Cambridge, UK 1958 (New)
- PSR-0450/03 KENO3D 5.1, Visualisation Tool for KENO V.A and KENO-VI Geometry Models (New version)
- PSR-0538/01 P-CARES 2.0.0, Probabilistic Computer Analysis for Rapid Evaluation of Structures (New)
For more details
see the daily updated list at www.oecd-nea.org/html/dbprog/cpsnew.html
5. Integral experiments data
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
The International Fuel Performance
Database was recently updated and now includes:
The March 2008 edition of the
Reactor Physics Benchmark Experiments (IRPHE) Project handbook is now
available at www.oecd-nea.org/html/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.
Reactor Shielding for Nuclear Engineers.
7. Training courses and workshops
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. For more information visit http://www.debftp.nri.cz/eng/index.html.
Note, the deadline for applying is 1 April 2008.
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. FLUKA 2008.3 release
13 -17 October 2008
Sensitivity and Uncertainty Analysis Training Course using SCALE
TSUNAMI, held at KFKI Budapest, Hungary. Syllabus. Registration
Form. - Accommodation, transportation, meeting place, and maps
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
Meetings and conferences Sponsored by the
Science Committee & Data Bank
9. Other items
Information on joint research projects related to
A steam explosion experiments
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.
To access the latest issue of the NEA
online bulletin, click here.