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OECD/NEA Data Bank
Computer Program Service (CPS) E-Newsletter
No. 21, December 2004
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 |
USCD1208/06
|
CHECKR-7.0
|
ENDF/B Format Check (New Edition)
|
USCD1209/06
|
FIZCON-7.0
|
ENDF/B Cross-Sections Redundancy Check
(New Edition)
|
USCD1212/06
|
INTER-7.0
|
ENDF/B Thermal Cross-Sections, Resonance
Integrals, G-Factors Calculation (New Edition)
|
USCD1216/06
|
PSYCHE-7.0
|
ENDF/B Data Consistency Check in ENDF
Format (New Edition)
|
USCD1218/06
|
STANEF-7.0
|
ENDF/B Book-keeping Operations for ENDF
Format Files (New Edition)
|
ESTS0198/01
|
FEM-3
|
Heavy Gas Dispersion Incompressible Flow
(New)
|
CCC-0601/03
|
GENII-LIN
|
Environmental Radiation Dosimetry System
(New)
|
NEA-1734/01
|
CRISSUE-S
|
Neutronics/Thermal-hydraulics
Coupling in LWR Technology (New)
|
NEA-0915/02
|
COGEND
|
Decay Data Generated in
ENDF-6 Format (New Edition)
|
NEA-1708/02
|
ADEFTA 2.0
|
Atomic Densities for Transport Analysis
(Tested)
|
NEA-1733/01
|
MCNP4B-GN
|
Monte Carlo Code System for (gamma,n)
production and trasport in high-Z materials (New)
|
NEA-1732/01
|
3D-TRANS-2003
|
Workshop on Common Tools and Interfaces
for Radiation Transport Codes (New)
|
NEA-1731/01
|
ZZ-BFBT
|
OECD/NEA-US/NRC NUPEC BWR Full-size
Fine-mesh Bundle Tests Benchmark (New)
|
NEA-1678/05
|
BOT3P4.1
|
3D Mesh Generator and Graphical Display
of Geometry for Radiation Transport Codes, Display of Results (New
Edition)
|
NEA-1686/01
|
ENTRÉE 1.4.0
|
BWR Core Simulation System for Space and
Time Dependent Coupled Phenomena (New)
|
NEA-1729/01
|
IFPE/IFA-507-TF3-TF5
|
Database For Transient Temperature
Experiment Ifa-507 (New Edition)
|
ESTS1300/02
|
E3D
|
3-D Elastic Seismic Wave Propagation Code
(Tested)
|
NEA-1677/01
|
IFPE/ZAPOROSHYE-V1K
|
Zaporoshye VVER1000 fuel behaviour data
(4-8 cycles, Burnup about 50 MWd/kgUO2) (New)
|
NEA-1486/03
|
ICSBEP-2004
|
International Criticality Safety Benchmark
Experiment Handbook (New Edition)
|
ESTS0551/01
|
TMAP4
|
Tritium Migration Analysis Program Version
4 (New)
|
NEA-1327/04/05
|
CAPCAL
|
3-D Capacitance Calculator for VLSI
Purposes (New Edition)
|
NEA-1707/02
|
ZZ MATXSLIBJ33
|
JENDL-3.3 based,175 N-42 photon groups
(VITAMIN-J) MATXS lib. for discrete ordinates multi-group (Tested)
|
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:
- The first technical review meeting relative to the
International Reactor Physics Benchmark Experiments Project ( IRPhE ) was held
from 27-28 October 2004 in Paris.
- The International Fuel Performance Experiments Database (IFPE) was recently updated with new experiments (18 October 2004).
- 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:
- Schools / Courses
- Training Courses for 2005
- TRIPOLI-4
planned for Winter 2005.
- PENELOPE 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.
- 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. (see
also:
http://mcavignon2005.cea.fr/
- Further announcements for possible
courses on MCNP5, MCNPX, SCALE5 and others will be made later. Future
courses, tutorials etc. will be held depending on user interest and
participation.
- Meetings Sponsored by the Nuclear
Science Committee & Data Bank
2005
- 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
- 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
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
General Chair: Ben Rouben (Atomic Energy of
Canada Ltd.)
Technical Program Chair: Dr. Kenneth S. Kozier (Atomic Energy of
Canada Ltd.)
Vancouver, Canada
Update from the Thermochemical Database
Project (TDB):
Four new NEA TDB Reviews stemming from Phase II of the Project are now
entering their final stage:
- The Reviews on the Chemical Thermodynamics
of Nickel and Selenium (inorganic species and compounds) are now with
the publisher and should be available in the first half of 2005.
- These two books will be followed shortly
by two further volumes dealing with the inorganic species and compounds
of
Zirconium and with the species and compounds formed by selected organic
ligands (EDTA, citrate, oxalate and ISA) with U, Np, Pu, Am, Tc, Se, Ni
and Zr.
Nuclear Data News
- JEFF-3.1
The NEA Data Bank organised a JEFF meeting 24-26 November where
approximately 50 people discussed the next version of the general
purpose library JEFF: JEFF-3.1. The data library is planned to be
released for benchmarking in
May of next year and by the end 2005 the final version is expected to
be
available for distribution.
Progress on the Decay Data and Fission Yields library was presented
during the JEFF meeting. The feedback from testing and benchmarking has
been collected and the version for distribution is expected to be
released along with the general purpose library JEFF3.1.
JEFF-3/A Activation file is available at the NEA (to request a DVD
copy: rugama@oecd-nea.org ).
- JANIS
Janis (Java-based nuclear information software) is a display program
designed to facilitate the visualisation and manipulation of nuclear
data. It allows the user to access numerical values and graphical
representations without prior knowledge of the storage format. It
offers maximum flexibility for the comparison of different nuclear data
sets.
It can be used locally on a PC or remotely connected to the NEA web
site.
The Janis NEA remote database has been updated to include these
libraries:
BROND-2.2, CENDL-2.1 (general purpose libraries, processed with
NJoy99.90 at 293.6K)
JEFF-3/A (Activation, interaction data)
JENDL-FP-DD 2000 (decay data, radioactive data)
JENDL-FY 3.3 (fission yields)
An upgrade to Janis 2.1 is available on the NEA web site:
http://www.oecd-nea.org/janis/download.html
or, to request a DVD copy:
http://www.oecd-nea.org/janis/orderform.html
You can also launch the new version online from the Janis web page: http://www.oecd-nea.org/janis , link
"Launch Janis 2.1".
News from the OECD Nuclear Energy Agency (NEA)
The latest issue of the NEA on-line bulletin.
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