OECD/NEA Data Bank E-Newsletter
No. 3, October 2008
On
1 October, a questionnaire concerning the Data Bank was sent out to the
delegates of member countries (all members of the Executive Group of
the Nuclear Science Committee: the Data Bank management committee).
This questionnaire was prepared for the first step in the revision
process of the Data Bank part of the next NEA Strategic Plan, a new
six-year plan.
The Physor'08, International Conference
on the Physics of Reactors, organised by PSI in collaboration with NEA,
was held in Interlaken, Switzerland from 14-19 September 2008. Many NEA
related works especially in relation with NSC were presented and
discussed. As to the nuclear data conference track, the recent release
of new versions of the major evaluated data libraries showed a
significant performance improvement, nevertheless data improvements are
still needed for the data of actinides particularly minor-actinide
cross-sections and fission spectra. Renewed interest was also observed
in covariance matrices. Many industrial applications of Nuclear Data
and calculation methods in reactor physics for power plants were
presented and discussed. Specific sessions were devoted to benchmark
studies carried out under the aegis of OECD/NEA.
Content:
- Nuclear data and tools
- Processed data
libraries
- Chemical thermodynamics
data
- Computer programs
- Integral experiments
data
- Benchmarks
- Training courses and
workshops
- Conferences
- Other items
1. Nuclear data and tools
A Nuclear Reaction Data Centres (NRDC) meeting
was
held in Obninsk, Russia on 22-25 September 2008. The topic of quality
control of EXFOR and CINDA, experimental and bibliographical databases,
was discussed extensively. The development of user feedback pages was
decided as a way of identifying EXFOR entries containing possible
errors. This will be helpful for creating a new data base that only
contains correct EXFOR entries, which will be a useful tool for the
evaluators of nuclear data.
2. Processed data libraries
Recently acquired or tested
application data
libraries:
- DLC-0220/01 ZZ HILO2K, Coupled 83
Neutron, 22 Photon Group Cross Sections for Neutron Energies Up to 2
GeV for ANISN, DORT and TORT
- IAEA-1423/01 ZZ PADF-2007, Proton
Activation Data File in ENDF-6 format
For a full list of processed cross-section data
libraries
visit www.oecd-nea.org/dbprog/categ-z.html.
For 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
4. Computer Programs
The most recently acquired or tested
computer
codes and application data libraries are:
- CCC-0641/06 NESTLE
5.2.1, Few-Group Neutron Diffusion for Steady-State and Transient
Problems by Nodal Expansion Method (NEM) (New)
- PSR-0375/01 COGAP, Nuclear Power
Plant Containment Hydrogen Control System Evaluation Code (New)
- CCC-0627/02 RADAC,
Radioactive Decay and Accumulation of Long Lived Isotopes (Updated version)
- IAEA-1408/03 WLUP3.0,
69 and 172 Group Cross Section Libraries for WIMS (Updated version)
- PSR-0522/01 TRUMP, Steady-State and
Transient 1-D, 2-D and 3-D Potential Flow, Temperature
Distribution (New)
- IAEA-1402/04 ENDVER-ENDVER/GUI
1.42, The ENDF File Verification Support Package (Updated version)
- NEA-1826/01 SOLTRAN, solving
multi-dimensional simplified P2 transport and diffusion problems of
hexagonal geometry in fast reactors (Tested)
- NEA-1716/06 TRIPOLI-4.3.3 &
4.4, Coupled Neutron, Photon, Electron, Positron 3-D, Time Dependent
Monte-Carlo, Transport Calculation (Updated version)
- CCC-0746/01 MCNPX
2.6.0, Monte Carlo All-Particle Transport Code System including
MCNPDATA and VISED Version X_22S (New)
For more details
see the daily updated list at
www.oecd-nea.org/dbprog/cpsnew.html.
5. Integral experiments data
Radiation shielding
- DLC-0196/01 ZZ PR-EDB, Power
Reactor Embrittlement Database
Reactor physics
The March 2008 edition of the
International
Reactor Physics Benchmark Experiments (IRPHE) Project handbook is now
available at
www.oecd-nea.org/science/wprs/irphe/.
The next IRPhE review meeting preparing the 2009 edition of the IRPhE
Handbook is scheduled for October 2008.
Criticality
The 2008 edition of the International
Criticality Safety Benchmark Evaluation Project (ICSBEP) was
released in September. You may request a DVD by accessing the
ICSBEP webpsite.
6. Benchmarks
- NEA-1827/01 GANAPOL-ABNTT,
Analytical Benchmarks for Nuclear Engineering Applications, Case
Studies in Neutron Transport Theory
7. Training courses and workshops
-
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
notes.
-
27-31 October 2008
Joint introductory/intermediate MCNP/MCNPX training course, GRS, Garching near Munich, Germany - co-sponsored
by ORNL/RSICC. Registration closed. Syllabus.
-
18 November 2008
Workshop on "Processing Tools for Evaluated Nuclear Data". OECD/NEA
Data Bank, Issy-les-Moulineaux, France.
For more information please visit www.oecd-nea.org/html/dbdata/meetings/nov2008/.
- 18-20 November 2008
JEFF meeting. OECD/NEA Data Bank, Issy-les-Moulineaux, France.
For more information please visit www.oecd-nea.org/html/dbdata/meetings/nov2008/.
- 21 November 2008
NJOY user
group meeting . OECD/NEA Data Bank, Issy-les-Moulineaux,
France.
- 2-6 March 2009
SCALE6
Lattice Physics and Depletion Course, OECD/NEA Data Bank - co-sponsored by ORNL/RSICC,
Issy les Moulineaux, France.
-
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. Registration
form.
- 23-27 March 2009
MCNP/MCNPX
Training course, OECD NEA Data Bank - co-sponsored by ORNL/RSICC,
Issy les Moulineaux, France. Registration
form. Syllabus.
8. Conferences
Meetings and conferences sponsored by the
Nuclear
Science Committee & Data Bank
2009
- 3-7 May 2009
M&C-2009,
ANS Mathematics and Computation Division, Saratoga
Springs, NY, USA.
Contact: Tom Sutton
-
7-10 June 2009
First International Conference on Advancements in Nuclear
Instrumentation, Measurement Methods and their Applications
ANIMMA, Marseille, southern France.
- 6-10 September 2009
GLOBAL-2009:
8th Global Congress on Nuclear Fuel Cycle: Sustainable Options and
Industrial Perspectives, Paris, France.
2010
- 9-14 May 2010
Physor-2010
Advances in Reactor Physics to Power the Nuclear Renaissance, Sheraton
Station Square Hotel, Pittsburgh, Pennsylvania, USA.
See also: Other
NEA nuclear science meetings
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.
To access the latest issue of the NEA
online bulletin, click here.