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OECD/NEA Data Bank
Computer Program Service (CPS) E-Newsletter
No. 32, February 2007
CO-OPERATIVE ARRANGEMENT NEA/US-DOE
The
co-operative arrangement
between US-DOE and the OECD/NEA concerning the exchange of computer
codes and nuclear data has now been implemented both at the Radiation
Shielding Information Computational Center (RSICC) and the NEA Data
Bank. The computer codes and associated data libraries
released by RSICC will once again be distributed by the
NEA Data Bank.
We all
look forward to a renewed and strong co-operation with RSICC.
END-USERS and END-USE STATEMENT
Starting March 2007, we have been asked to identify end-users of the packages we distribute
(the end-user is the person who will be using the software in your establishment). We
also need a statement on the applications/reasons for which this
information will be used. From now on, requesters must provide this
information at the time they place the request.
Computer Program Service of the OECD/NEA
Data Bank
Content:
- New computer codes & related
information
- Integral Experiments
- Workshops, training courses &
tutorials,
meetings
The most recently acquired or tested computer
codes
and data libraries are:
| Identification |
Name |
Description |
Computer
Codes and associated Data Libraries
|
NEA-1688/04
|
SACALC_CYL |
Calculates the average
solid angle subtended by a volume (Tested) |
| IAEA1388/05 |
FOTELP-2K6 |
Photons, Electrons and Positrons
Transport in 3D by Monte
Carlo Techniques (New Version) |
| NEA-1561/10 |
CHEMENGL/CHIMISTE |
Chemical and Physical Properties of
Elements (New Version) |
| CCC-0730/01 |
MCNP/MCNPX |
Monte Carlo Particle Transport Code
System Including MCNP5 1.40, MCNPX 2.5.0, VISED19L and Data Libraries (New) |
| CCC-0732/01 |
SCALE5.1/ORIGEN |
Modular system for criticality,
shielding, source term, fuel depletion/decay, reactor physics (New) |
| CCC-0707/02 |
PARTISN 4.0 |
1-D, 2-D, 3-D Time-Dependent, Multigroup Deterministic Parallel Neutral Particle Transport Code
(New) |
| CCC-0638/09 |
TART2005 |
3D Coupled N-Photon Combinatorial Geometry Time Dependent Monte Carlo Transport Code
(New) |
| CCC-0721/01 |
GRTUNCL3D |
Code to Calculate Semi Analytic First Collision Source and Uncollided Flux (X, Y, Z)
(New) |
| PSR-0534/01 |
PUFF-IV |
Code System to Generate Multigroup Covariance Matrices from ENDF/B-VI Uncertainty Files
(New) |
| NEA-1678/08 |
BOT3P5.2 |
3D Mesh Generator and Graphical Display of Geometry for Radiation Transport Codes, Display of Results
(New Version) |
| NEA-1708/04 |
ADEFTA 3.1 |
Atomic Densities for Transport Analysis (New Version) |
| NEA-1779/01 |
SAGEP-FR |
Sensitivity Analysis of Fast Reactor Parameters (New) |
NEA-0850/17
|
ECIS-06
|
Coupled Channel, Statistical Model, Schroedinger and Dirac Equation, Dispersion Relation (New Version)
|
| Integral
Experiments Data |
| CSNI2008/01 |
MASCA |
In-vessel phenomena during severe accidents (New) (Restricted
Distribution) |
| CSNI2003/01 |
MCCI PROJECT |
Molten Core Concrete Interaction Project (New) (Restricted
Distribution) |
NEA-1741/02
|
IFPE/NOVOVORONEZH-R1 |
operation factor data of the Novovoronezh VVER-1000 fuel
assembly 4108 rods (Updated
Edition)
|
NEA-1774/01
|
IFPE/FMDP-MOX4-5 |
Weapons-Derived MOX Fuel DOE FMDP Test Irradiations
Capsules 4 & 5, Advanced Test Reactor (ATR) (New)
|
NEA-1629/01
|
IFPE/IFA-508 & 515 |
PCMI Behaviour of Thin Cladding Rods, JAERI and HRP (New Archive)
|
NEA-1736/01
|
IFPE/GBGI |
Grain-Bubble Gas Interlinkage (New Archive)
|
| NEA-1780/01 |
PWR-MOX/UOX-TRANS |
OECD/NEA US-NRC PWR MOX/UO2 Core Transient Benchmark (New) |
For
more details see daily updated list
Poll: In view of adapting
our service to changing technologies we are carrying out a poll with
our users to verify, whether or not they can read DVDs. Please provide here
your answer to our query.
Integral Experiments Data for Model
and Code Validation:
- 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 1187 cases
(6 March 2007). Since then new experiments were released in particular
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: 5
January 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. The next edition will be
issued in March 2007.
- 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 and the OECD/NEA MASCA Project have been released and are
available to authorised users.
Workshops, training courses &
tutorials planned for 2007:
- Schools / Courses / Workshops
- 7 May
2007
Introduction
to MCNP using the Visual Editor in Richland, Washington,
USA.
- 16
July 2007
Advanced
class on the Visual Editor, CAD to MCNP conversion and data
Visualization using Excel,
Please contact Randy Schwarz for more information: randyschwarz@mcnpvised.com
or http://www.mcnpvised.com
- Further announcements for possible
courses on SCALE5,
TRIPOLI-4, MCNP/MCNPX,
PENELOPE and others
will be made later.
Future courses, tutorials etc. will be held depending on user interest
and participation.
- Courses / Workshops held in 2006 and 2007
- 12-16 March 2007
MCNP5 Introductory Class, with additional topics in advanced geometry &
criticality, University of Pisa, Italy, OECD NEA Data Bank
- co-sponsored by ORNL/RSICC (Information on accommodation and
transportation). (Registration closed now)
- 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
- 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).
Organiser: Georgia Institute of Technology, Callaway Gardens
- 21-23 April 2009
SATIF-9, Shielding Aspects of
Accelerators, Targets and Irradiation Facilities -
Spallation Neutron
Source, SNS, 701 Scarboro Road, OAK RIDGE, TN, USA
- 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
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