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OECD/NEA Data Bank
Computer Program Service (CPS) E-Newsletter
No. 26, December 2005
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 |
NEA-1553/40
|
SINBAD/MEPHI
|
MEPhI empty slits streaming experiment (1995-1998) (New)
|
NEA-1673/01/02
|
MVP/GMVP II
|
MC Codes for Neutron Photon Transport Calc. based on Continuous Energy and Multigroup Methods (New)
|
NEA-1755/01
|
SCIP V1.1
|
Radioactive Surface Contamination Investigation Program
|
NEA-1601/01
|
GARDEC
|
Estimation of dose-rates reduction by garden decontamination
|
NEA-1697/01
|
IFPE/HATAC |
Fission Gas Release at High Burn-up, Effect of a Power
Cycling (New) |
IAEA1285/05
|
EPICSHOW |
Interactive Viewing of EPIC (Electron Photon Interaction
Code) Data Library (Tested) |
IAEA1388/04
|
FOTELP-2K3 |
Photons, Electrons and Positrons Transport in 3D by Monte
Carlo Techniques (Tested) |
IAEA1395/05
|
XNWLUP |
Graphical user interface to plot WIMS-D library
multigroup cross sections (Tested) |
ESTS1049/02
|
NRCPIPES |
Fracture Mechanics of Cracked Pipes (Tested) |
ESTS1100/02
|
HABIT |
Toxic and Radioactive Release Hazards in Reactor Control
Room (Tested) |
| IAEA0940/01 |
JADSPE |
Multi-Channel Gamma Spectra Unfolding Program (Tested)
|
| IAEA1401/01 |
ZZ DROSG-2000 |
Legendre Coefficient Library for 59 monoenergetic neutron
source reactions (Tested) |
| IAEA1402/03 |
ENDVER-ENDVER/GUI |
The ENDF File Verification Support Package (Tested)
|
IAEA1407/01
|
ZZ RRDF-98 |
Cross-sections and covariance matrices for 22 neutron
induced dosimetry reactions (Tested) |
IAEA1412/02
|
ZZ-MINSKACT |
Evaluated neutron reaction data for Th-232, Pa, U, Np,
Pu, Am and Cm isotopes (Tested) |
NEA-1278/03
|
CALENDF-2002 |
Pointwise, Multigroup Neutron Cross-Sections and
Probability Tables Production from ENDF/B Evaluations (Tested) |
NEA-1711/01
|
DORTDAT2 |
Input-Making Support System for a Two-Dimensional SN
Code, DORT (Tested) |
NEA-1676/05
|
ERRORJ |
Multigroup covariance matrices generation from ENDF-6
format (Tested) |
IAEA1415/01
|
IRPHE-KNK-II-ARCHIVE |
KNK-II fast reactor documents, power history and measured
parameters (New) |
| IAEA1419/01
|
ZZ
IBANDL |
Ion
Beam Analysis Nuclear Data Library in R33 format (Tested) |
| IAEA1418/01
|
ZZ
INDL/TSL |
Thermal
Neutron Scattering Data for H2O, D2O and ZrHx in ENDF-6 Format and as
MCNP(X) Data Sets (Tested) |
| ESTS0219/07 |
TOUGHREACT |
Chemically reactive
non-isothermal flows of multiphase fluids in porous and fractured media
(New) |
| ESTS0219/08 |
TMVOCV1.0
|
Multicomponent,
multiphase, nonisothermal flows of water (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 International Fuel Performance Experiments Database (IFPE) contains 851 cases
(21 October 2005).
- The Shielding Benchmark Experiments Database (SINBAD) includes 36 Reactor Shielding-27 Fusion Neutronics
Shielding-, and 13 Accelerator Shielding-Experiments. (last update: 16 December 2005).
- 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 project, the SETH Project and the PSB-VVER
Project). These data are subject to restrictions for
their distribution.
Workshops, training courses
tutorials planned for 2006:
- 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.
- 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
- 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)
- 15-17 May 2006
TOUGH
Symposium 2006, Lawrence Berkeley National Laboratory, Berkeley,
California
- PENELOPE-2006 Barcelona, early July
2006, (programme is being prepared).
- 15-17 September 2006
Workshop on Use of Monte Carlo Techniques for Design and Analysis of
Radiation Detectors, University of Coimbra, Coimbra, Portugal
- Courses / Workshops recently held
- NJOY
Workshop and User Group Meeting, 2 May 2005, NEA headquarters, 12
boulevard des Iles , 92130 Issy les Moulineaux, France (Proceedings)
- PENELOPE
4-7 July 2005,
Scope
Objectives and Syllabus
- 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 has
focussed 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
- 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.
- 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.
- Workshop on Processing
of Application Libraries for Monte Carlo Transport Calculations,
12-16
September 2005, IAEA, Vienna, Austria
- On request, the handouts of the Workshop on
Advances in Monte Carlo
Criticality
Calculations, and Workshop on the Monte Carlo Code
TRIPOLI-4 are available on CD-ROM to authorised users from
NEA Data Bank member countries
- Workshop on Evaluation of Uncertainties in Relation to Severe Accidents and Level 2
Probabilistic Safety
Analysis, Cadarache (France), 7-9 November 2005
- Meetings Sponsored by the Nuclear
Science Committee Data Bank
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
- 22-24 May 2006
Shielding Aspects of Accelerators, Targets and
Irradiation Facilities - SATIF-8
Chair: Hee-seock LEE
Pohang Accelerator Laboratory POSTECH, Korea, Rep.
- 5-7 September 2006
CFD4NRS: Workshop on Benchmarking of
CFD Codes for Application to
Nuclear Reactor Safety, OECD/NEA and IAEA, hosted
by Gesellschaft für
Anlagen- und Reaktorsicherheit (GRS), Garching, Munich, Germany
- 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)
- 25-29 September 2006
9th Information Exchange Meeting on Actinide and Fission Product
Partitioning and Transmutation (co-organised NSC/NDC)
Nîmes, France
- 1-4 October 2006
3rd
International Topical Meeting on High Temperature Reactor Technology -
HTR 2006,
Potchefstroom, South Africa

2007
- 15-18 April 2007
SNA-2007
+ MC-2007, Joint International Conference 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
Contact: Doug Vogt
- 22-27 Avril 2007
Nuclear Data Conference
ND-2007
Nice, France
- 28-31 May 2007
Eighth
International Conference on Nuclear Criticality Safety - ICNC-2007
Saint Petersburg, Russia
2008
- 14-18 September 2008
PHYSOR-2008-
Nuclear Power: A Sustainable Energy Resource
Interlaken, Switzerland
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