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OECD/NEA Data Bank
Computer Program Service (CPS) E-Newsletter
No. 31, December 2006
Computer Program Service of the OECD/NEA
Data Bank
Content:
- New computer codes & related
information
- Integral Experiments
- Workshops, training courses &
tutorials,
meetings
- Nuclear Data News
The most recently acquired or tested computer
codes
and data libraries are:
| Identification |
Name |
Description |
NEA-1517
|
SINBAD-NAIADE-H2O-60
|
Fission neutron
propagation in light water source diameter 60 cm (New)
|
NEA-1517
|
SINBAD-NAIADE-FE-C60
|
Fission neutron
propagation in iron and graphite source diameter 60 cm (New) |
NEA-1278
|
CALENDF-2005
|
Pointwise, Multigroup
Neutron Cross-Sections and Probability Tables from ENDF/B Evaluations
(New) |
NEA-1746
|
ZZ-PBMR-400
|
OECD/NEA PBMR Coupled
Neutronics/Thermal Hydraulics Transient Benchmark - The PBMR-400 Core
Design (Updated edition) |
NEA-1775
|
ZZ-CLES |
Cross section library of
moderator materials for low-energy neutron sources (New) |
NEA-1772
|
IFPE/IFA-597-MOX |
Hollow and solid MOX rods
experiments (New) |
NEA-1697
|
IFPE/HATAC |
Fission Gas Release at
High Burn-up, Effect of a Power Cycling (Updated edition) |
NEA-1424
|
ZZ FSXLIBJ33 |
MCNP nuclear data library
based on JENDL-3.3 (Updated edition) |
NEA-1688
|
SACALC_CYL |
Calculates the average
solid angle subtended by a volume (New) |
NEA-1771
|
BULK_C-12 |
Neutron and photon
effective dose rates from medium energy protons
or carbon ions through concrete or concrete/iron (New) |
For
more details see daily updated list
Integral Experiments Data for Model
and Code Validation:
The home page for
Compilations
and Evaluations has been updated concerning:
- The 2006 edition of the International Criticality Safety
Benchmark Evaluation Project (ICSBEP)
has been released in September. It contains now experimental data for
3955 critical configurations.
- The International Fuel Performance Experiments Database (IFPE)
contains 1183 cases
(6 June 2006). Since then new experiments were released in pareticular
relative to MOX fuels which are in process of being compiled and
evaluated. They shall be integrated into IFPE during 2007.
- The Shielding Benchmark Experiments Database (SINBAD)
includes 41 Reactor Shielding, 27 Fusion Neutronics
Shielding, and 15 Accelerator Shielding Experiments (last update: 15
December 2006). The latest additions are the three NAIADE (Graphite,
Iron and Water) experiments released by CEA France. Experiments
on photon
emission spectra and several experiments related to accelerators, e.g.
from the
CERF facility are being compiled at present and shall
be integrated into SINBAD during 2007.
- The first edition of the International Handbook of
Evaluated Reactor Physics Benchmark Experiments Handbook (IRPhE) was published in March 2006 and
contains reactor physics benchmark specifications that have been
derived from experiments that were performed at various nuclear
experimental facilities around the world. A Technical Review Committee
discussed at the end of October a series of new experiments, it carried
out further evaluation work that will be included in the second
edition of the Handbook scheduled for March 2007. A description of the
principles and methods used in the production of the Handbook are
provided in the summary
of this meeting.
- The experimental data and reports from recent projects
operated
under the auspices of the Committee on the Safety of Nuclear
Installations
(CSNI) have been added to the Data Bank. (These comprise the CABRI REPNa
series , the SETH Project and the PSB-VVER
Project). These data are subject to restrictions for
their distribution at this stage. The reports and data from the RASPLAV
project are available to organisations from OECD member
countries and from the
Russian Federation. Additional experimental data from the OECD/NEA Melt Coolability and
Concrete Interaction (MCCI) Project have been released and will be
available to authorised users in 2007.
Workshops, training courses &
tutorials planned for 2007:
- Schools / Courses / Workshops
- 22 January - 9 February 2007
Seminar
and Training on Scaling, Uncertainty and 3D Coupled Code Calculations
in Nuclear Technology, (3D.S.UNCOP-2007), Department of
Nuclear Engineering of Texas A&M, College Station, Texas, USA
- 12-16 March 2007
MCNP5
Introductory Class, with additional topics in advanced geometry &
criticality, University of Pisa, Italy - Programme of Training Course - (Information on accommodation and
transportation).
- Further announcements for possible
courses on SCALE5,
TRIPOLI-4 and others will be made later.
Future courses, tutorials etc. will be held depending on user interest
and participation.
- Courses / Workshops held in 2006
- 28-29 November 2006
Journées "codes de calcul en radioprotection, radiophyisque et
dosimétrie", INSTN, Saclay
- 20 November
2006
NJOY
users group
meeting, NEA
Headquarters, Issy-les-Moulineaux, France (Link contains Proceedings)
- 15-17 November 2006
Training Course on Montecarlo Simulation, Universidad Internacional de
Andalucía, Baeza (Jaén), Spain
- 15-17 September 2006
Workshop on Use of Monte Carlo Techniques for Design and Analysis of Radiation Detectors,
University of Coimbra, Coimbra, Portugal
- 28-31 August 2006
The OECD Halden Reactor Projects organises every year an International
Summer School. The next one is called OECD
- HRP Summer School on Water
Chemistry of Nuclear Reactor Systems, held at Halden,
Norway. The
deadline for registration is June 30.,
(Programme)
- 23 August - 1 September 2006
Frédéric
Joliot/Otto Hahn Summer School on Nuclear Reactors: Physics, Fuels, and
Systems, CEA Cadarache, France
- 17-21 July 2006
Intermediate Workshop on MCNPX, ENEA, Bologna, Italy.
- 4-7 July 2006
PENELOPE-2006,
University of Barcelona, Barcelona, Spain. Scope Objectives and Syllabus.
- 15-17 May 2006
TOUGH
Symposium 2006, Lawrence Berkeley National Laboratory,
Berkeley, California, USA
- 7-8 April 2006
Training
Course on Neutron Spectra
Unfolding, Cape
Town, South Africa: UMG software
package provided by PTB (UMG:
Unfolding with GRAVEL and MAXED)
- 23 January - 10 February 2006
Seminar and Training on Scaling,
Uncertainty
and 3D Coupled Code Calculations in Nuclear Technology,
(3D.S.UNCOP-2005), School of
Nuclear Engineering, Barcelona, Spain
- Meetings Sponsored by the Nuclear
Science Committee & Data Bank
2007
- 15-19 April 2007
SNA-2007 +
M&C-2007, Joint International Topical Meeting on Mathematics
&
Computation and Supercomputing in Nuclear Applications
Monterey Marriott, Monterey, California, USA
General Chair: Tomas Diaz de la Rubia and Brian Wirth (Lawrence
Livermore National Laboratory)
Technical Program Chair: Jasmina Vujic (University of California,
Berkeley)
Monterey, California, USA
- 9-13 September 2007
GLOBAL-2007
Boise, Idaho, USA
Contact: Teri Ehresman
2008
- 13-17 April 2008
Eleventh International Conference on Radiation
Shielding (ICRS11) and
Fifteenth Topical on Radiation Protection and Shielding (RPS15).
Orhaniser: Georgia Institute of Technology, Callaway Gardens
- 25-30 May 2008
13th
International Symposium on Reactor Dosimetry
Akersloot, Netherlands
2009
- 3-7 May 2009
M&C-2009, ANS
Mathematics and Computation Division
Saratoga Springs, NY. USA
Contact: Tom Sutton
The JEFF-3.1 Nuclear Data Library is the latest version of the Joint
Evaluated Fission and Fusion Library issued by the Data Bank.
The complete JEFF-3.1 Library suite contains:
- Incident Neutron Data for 381 materials from 1-H-1 to
100-Fm-255
- Incident Proton Data for 26 materials
- Radioactive decay data for 3852 isotopes
- Neutron Induced and Spontaneous Fission Yield Library
- Activation Library
- Thermal Scattering Data for 9 materials
The documentation "The
JEFF-3.1 Nuclear Data Library", JEFF Report 21, Data Bank, 2006,
ISBN 92-64-02314-3, 130 pages was published recently. A limited number
of hard copies are available. The corresponding
Web page
provides further information on the content of the document and the
procedure to download the full report. A CD-ROM with the complete
library can also
be requested free of charge at the project Web page.
Three ACE format (Monte Carlo) data libraries based on JEFF-3.1 have
been
released in recent months (see complete
list
of ACE libraries). Not all contain processed data for all nuclides
and materials. Other libraries, based on JEFF-3.1 for
deterministic codes are in preparation and will be released during
2007.
News from the OECD Nuclear Energy Agency (NEA)
The latest issue of the NEA on-line bulletin.
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