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OECD/NEA Data Bank
Computer Program Service (CPS) E-Newsletter
No. 24, July 2005
Computer Program Service of the OECD/NEA
Data Bank
Content:
- New computer codes & related
information
- Integral Experiments
- Workshops, training courses &
tutorials,
meetings
- Thermochemical Database (TDB)
- Nuclear Data News
The most recently acquired or tested computer
codes
and data libraries are:
| Identification |
Name |
Description |
NEA-1738/01
|
IFPE/US-PWR-16X16LTA
|
IFPE/US-PWR-16X16
LTA (lead test assembly) Extended Burnup
Demonstration Program (New)
|
NEA-1552/20
|
SINBAD-ISIS800 |
ISIS Benchmark Experiment on Deep-Penetration Neutrons
through Concrete and Iron Shields (1998) (New) |
NEA-1680/03
|
PASCAL
|
Probabilistic Fracture Mechanics Analysis
of Structural Components in Aging LWR (New)
|
NEA-1684/02
|
IFPE/IFA-534.14REV1
|
Fission
gas release as a function of burnup at high power (52-55 MWd/kg) (New)
|
IAEA1417/01
|
W-SHIELDER
|
calculates
shielding thickness of water for photon emitting radionuclide between
0.5 to 10 MeV (New) |
NEA-1740/01
|
ZZ MATJEF22.BOLIB |
JEF-2.2 Multigr Coupled (199n + 42gamma) X-Section Lib.
in MATXS Fmt for Nuclear Fission Applications (New) |
NEA-1690/01
|
GRTUNCL-3D/R-THETA-Z
|
Code
to Calculate Semi Analytic First Collision Source and Uncollided
Flux in an R-theta-Z grid (New) |
NEA-1678/06
|
BOT3P5.0
|
3D
Mesh Generator and Graphical Display of Geometry for Radiation
Transport Codes, Display of Results (New) |
NEA-1564/07/08
|
EASY-2003
|
European
Neutron Activation System (New) |
NEA-1693/03
|
ZZ V1000CT-1&2 |
VVER-1000 Main Coolant Pump (MCP) Switching On Benchmark
(Revised Edition)
|
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 International Fuel Performance Experiments Database (IFPE) was updated with new experiments and contains now 851 cases
(1 June 2005).
- The Shielding Benchmark Experiments Database (SINBAD) includes now 35 Reactor Shielding, 26 Fusion Neutronics
Shielding and 12 Accelerator Shielding Experiments. (last update: 14
June 2005). A
new version will be
included in the near future.
- 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
Workshops, training courses &
tutorials planned for 2005:
- Courses / Workshops
- Training Courses for 2005
- PENELOPE 4-7 July 2005, Scope
& Objectives and Syllabus, Registration
Form .
- Seminar and Training on Scaling,
Uncertainty
and 3D Coupled Code Calculations in Nuclear Technology,
(3D.S.UNCOP-2005) University
of Zagreb, 20 June - 8 July 2005
- Workshop on Advances in Monte Carlo
Criticality
Calculations, Avignon, France, 11 September 2005.
This workshop will focus on recent advances in methods, codes, and data
for
Monte
Carlo criticality calculations, including: improvements to MCNP5 kcode
calculations, source entropy as a convergence diagnostic, Weilandt
acceleration, stochastic geometry for HTGRs, use of mesh tallies for
reactor
applications, pre-ENDF/B-VII data, Doppler broadening, material
composition
library, etc. Presenters will be Forrest Brown & Russell
Mosteller from the MCNP
development
team, X5 at LANL (see also:http://mcavignon2005.cea.fr/workshops_monte_carlo.htm)
- Workshop on the Monte Carlo Code
TRIPOLI-4 , Avignon, France, 11 September 2005, by the TRIPOLI-4
team. The TRIPOLI-4 Monte Carlo transport code (neutron, gamma,
electron/positron) is dedicated mainly to shielding, core physics and
criticality studies. The workshop will be centered on the following
topics:
- description of the main
capabilities/characteristics: geometry, material, source,
- cross-sections, biasing techniques,
estimators/scoring, …
- overview on programming features: language,
architecture, parallelism
- overview on validation: experimental benchmarks and
inter-code comparisons
Presentation of some realistic studies carried out with TRIPOLI-4
and of future functionalities. (see also: http://mcavignon2005.cea.fr/workshop_tripoli.htm)
- APOLLO2 Workshop, Avignon,
11 September 2005 from 1.30 PM to 4.30 PM presented by Igor Zmijarevic
& APOLLO2 team members (CEA). Apollo2 is a widely used, general
purpose transport code for assembly and core calculations. This
workshop will give an overall view of the models implemented in the
code and focus on recent developments, such as in self-shielding
formalism, acceleration techniques for the method of characteristics,
multigroup calculation in a large number of groups, 2D core
calculations, etc. The qualification program of Apollo2 will be
presented together with some recent applications. (see also: http://mcavignon2005.cea.fr/workshops_apollo.htm)
- Workshop on Processing
of
Application Libraries for Monte Carlo Transport Calculations, 19-23
September 2005, IAEA, Vienna, Austria
- Workshop on Evaluation
of Uncertainties
In Relation to Severe Accidents and Level 2 Probabilistic Safety
Analysis, Cadarache (France), 7-9 November 2005
- Further announcements for possible
courses
on MCNP5, MCNPX, SCALE5,
TRIPOLI-4 and others will be made later.
Future courses, tutorials etc. will be held
depending on user interest and participation.
- NJOY
Workshop and User Group Meeting, 2 May 2005, NEA headquarters, 12
boulevard des Iles , 92130 Issy les Moulineaux, France (Proceedings)
- Meetings Sponsored by the Nuclear
Science
Committee & Data Bank
2005
- 21-26 August 2005
ICENES 2005 – 12th International Conference on Emerging
Nuclear Energy Systems
Metropole Hotel, Brussels, Belgium
- 28 August - 1 September 2005
Accelerator Applications - AccApp’05
San Servolo, Venice, Italy
http://accapp05.infm.it/
- 12-15 September 2005
Topical Meeting Mathematics & Computation,
Supercomputing, Reactor Physics and Nuclear and Biological Applications
- M&C 2005
Avignon, Palais des Papes, France
http://mcavignon2005.cea.fr/
- 19-23
September 2005
Sixth
International Conference on WWER Fuel Performance, Modelling and
Experimental Support
Albena, Bulgaria
- 2-6 October 2005
Nureth 11 - Nuclear Reactors Thermal-Hydraulics
Avignon
SFEN and SFANS (French section of the American
Nuclear Society) in cooperation with CEA
- 9-13 October 2005
7th International Conference GLOBAL 2005
Tsukuba, Ibaraki-ken, Japan
Meetings held
- 16-18 February 2005
Advanced Reactors with Innovative Fuels - ARWIF-2005
Oak Ridge, USA
- 17-21 April 2005
ANS International Conference “Monte Carlo 2005” -
The Monte Carlo Method: Versatility Unbounded in a Dynamic Computing
World,
Chattanooga, Tennessee, USA
http://meetingsandconferences.com/MonteCarlo2005/
- 8-13 May 2005
The Twelfth International Symposium on Reactor Dosimetry
Park Vista Resort in Gatlinburg, Tennessee, USA
http://www.reactordosimetry.com/
- 15-19 May 2005
2005 International Congress on Advances in Nuclear Power
Plants (ICAPP’05)
Grand Inter-Continental Seoul, Korea
2006
- 3-6 April 2006
14th Biennial Topical Meeting of the ANS Radiation
Protection and Shielding
Division
General Chair: Dr. Chuan Fu Wu (Department of
Energy)
Technical Program Chair: Dr. Robert Hayes
(Westinghouse TRU Solutions)
Carlsbad, New Mexico, USA
http://www.ans-rpsw-carlsbad.com
- 22-24
May 2006
Shielding Aspects of Accelerators, Targets and
Irradiation Facilities - SATIF-8
Chair: Hee-seock LEE
Pohang Accelerator Laboratory POSTECH, Korea, Rep.
http://www.oecd-nea.org/science/meetings/SATIF-8/satif8.html
- 10-14 September 2006
PHYSOR-2006
Topical Meeting Advances in Nuclear Analysis and
Advances in Nuclear
Analysis and Simulation
Hyatt Regency Vancouver
General Chair: Ben Rouben
(Atomic Energy of Canada Ltd.)
Technical Program Chair: Dr. Kenneth S. Kozier (Atomic Energy of
Canada Ltd.)
Vancouver, Canada
Call for Papers
(PDF)
Two new reviews were published
in April by the Thermochemical Database Project (TDB): Chemical
Thermodynamics of Nickel and Chemical Thermodynamics of
Selenium. The TDB database has been consequently updated with new
files which can be downloaded from the NEA website by registered users.
Registered users can access
the new data files at the TDB webpage.
Previous volumes in the series examined the chemical thermodynamics of
Uranium, Neptunium, Plutonium, Americium and Technetium.
For more information, contact the TDB
Project Coordinator: tdb@oecd-nea.org
The JEFF-3.1 Nuclear Data Library is the latest version of the Joint
Evaluated Fission and Fusion Library. The complete suite of data was
released in May 2005, and contains general purpose nuclear data
evaluations compiled at the NEA Data Bank in co-operation with several
laboratories in NEA Data Bank member countries. JEFF-3.1 contains also
radioactive decay data, activation data and fission yields data. It
combines the efforts of the JEFF and EFF Working Groups who have
contributed to this combined fission and fusion file.
- The complete JEFF-3.1 Library suite contains:
- Incident Neutron Data for 381 materials from 1-H-1 to
100-Fm-255
- Thermal Scattering Data for 9 materials
- Incident Proton Data for 26 materials
- Radioactive decay data for 3852 isotopes
- Neutron Induced Fission Yields Library
- Spontaneous Fission Yields Library
- Activation Library
The library can be downloaded in its entirety as a single file or one
file per isotope from the web: http://www.oecd-nea.org/dbdata/.
A CD-ROM of the complete library can also be requested free of charge.
contact: data@oecd-nea.org
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