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OECD/NEA Data Bank
Computer Program Service (CPS) E-Newsletter
No. 22, February 2005
Computer Program Service of the OECD/NEA
Data Bank
Content:
- New computer codes & related
information
- Integral Experiments
- Workshops, training courses &
tutorials,
meetings
The Data Bank computer program and nuclear
data services celebrated their 40th
anniversary in 2004.
Since then more than 70 000 copies of computer program packages were
distributed to about 600 establishments
and scientists in member countries have also had free access to a very
large collection of bibliographic, experimental and evaluated nuclear
data.
More detailed
statistics in graphical concerning acquisitions and
distribution of computer codes during 2004 can be found here.
The most recently acquired or tested computer
codes
and data libraries are:
| Identification |
Name |
Description |
USCD1208/06
|
CHECKR-7.0
|
ENDF/B Format Check
(Tested)
|
USCD1209/06
|
FIZCON-7.0 |
ENDF/B Cross-Sections Redundancy Check
(Tested)
|
USCD1212/06
|
INTER-7.0
|
ENDF/B Thermal Cross-Sections, Resonance
Integrals, G-Factors Calculation (Tested)
|
USCD1216/06
|
PSYCHE-7.0
|
ENDF/B Data Consistency Check in ENDF
Format (Tested)
|
USCD1218/06
|
STANEF-7.0
|
ENDF/B Book-keeping Operations for ENDF
Format Files (Tested)
|
NEA-1735/01
|
CARL2
|
radiotoxicity, activity, dose and decay
power calculations for spent fuel (New)
|
USCD1207/22/23
|
PHREEQC 2.10
|
Modeling of Geochemical Reactions,
Calculation of pH, REDOX Potential (Tested)
|
USCD1207/21
|
PHREEQCI 2.10.0.0
|
Windows Interactive Version of PHREEQC (Tested)
|
USCD1207/20
|
PHRQCGRF
|
code to create graphs from the data
generated by PHREEQC (Tested)
|
NEA-1660/05
|
IRPHE-SNEAK
|
KFK SNEAK Fast Reactor Experiments,
Primary Documentation (Revised
Edition)
|
ESTS0637/01
|
DSEM
|
Radioactive Waste Disposal Site Economic
Model (Tested)
|
NEA-1517/69
|
SINBAD-VENUS-3
|
VENUS-3 LWR-PVS Benchmark Experiment
(New) |
NEA-1552/15
|
SINBAD-PSI-P590MEV
|
High Energy Neutron Spectra Generated
by 590-MeV Protons on a Thick Lead Target (New) |
NEA-1553/39
|
SINBAD-IPPE-FE |
IPPE neutron
transmission benchmark experiment with 14 MeV neutrons through iron
shells (New)
|
NEA-1669/03
|
ZZ MCB-ENDF/B6.8
|
MCB Continuous-Energy Neutron Cross
Section Libraries for Temperatures from
300 to 1800 K (DVD version)
|
NEA-1670/04
|
ZZ MCB-JENDL-3.2
|
MCB Continuous-Energy Neutron Cross
Section Libraries for Temperatures from
300 to 1800 K (DVD version)
|
NEA-1724/01
|
IFPE/NSRR-FK1-2-3
|
Behaviour of 3 BWR segments FK-1, FK-2
& FK-3 under RIA test conditions in NSRR (New)
|
For
more details see weekly updated list (on Mondays)
Integral Experiments Data for Model
and Code Validation:
The home page for
Compilations
and Evaluations has been updated concerning:
- A revised edition of the format
in which
the International
Reactor Physics Experiments Evaluation Project( IRPhE ) data are
presented and guidelines
for compilation, evaluation and review (Revision 8.8) was issued
recently.
- The International Fuel Performance Experiments Database (IFPE) was recently updated with new experiments and contains now 831 cases
(28 February 2005).
- The Shielding Benchmark Experiments Database (SINBAD) includes now 35 Reactor Shielding, 26 Fusion Neutronics
Shielding and
9 Accelerator Shielding Experiments. (last update: 15 December 2004).
- 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 now 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
- NJOY
Workshop and User Group Meeting, 2 May 2005, NEA headquarters, 12
boulevard des Iles , 92130 Issy les Moulineaux, France
- 4-7 July 2005, Scope
& Objectives and Syllabus, Registration
Form.
- Workshop on Using MCNP5 for Medical Physics
Applications, sponsored by Computational Medical Physics Working
Group on Sunday, April
17, 2005, 1-5pm. Participation is free. It is held in conjunction
with
the Monte Carlo 2005 Conference; Chattanooga Convention Center, Chattanooga, Tennessee, USA.
- Seminar and Training on Scaling,
Uncertainty
and 3D Coupled Code Calculations in Nuclear Technology, 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 at LANL (see also:
http://mcavignon2005.cea.fr/ )
- 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/)
- APOLLO2 Workshop, Avignon,
15 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/)
- 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
- Meetings Sponsored by the Nuclear
Science
Committee & Data Bank
2005
- 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
- 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/
- 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
http://www.oecd-nea.org/html/science/meetings/ARWIF2004/index.html
2006
- 2-5 April 2006
2006
Biennial Radiation and Shielding Topical Meeting
(RPS 2006)
General Chair: Dr. Chuan Fu Wu (Department of
Energy)
Technical Program Chair: Dr. Robert Hayes
(Westinghouse TRU Solutions)
Carlsbad, New Mexico, USA
- 22-24 May 2006
Shielding Aspects of Accelerators, Targets and
Irradiation Facilities - SATIF-8
Chair: Hee-seock LEE
Pohang Accelerator Laboratory POSTECH, Korea, Rep.
- 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
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