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OECD/NEA Data Bank
Computer Program Service (CPS) E-Newsletter
No. 25, September 2005
Computer Program Service of the OECD/NEA
Data Bank
Content:
- New computer codes & related
information
- Integral Experiments
- Workshops, training courses &
tutorials,
meetings
- Results of polling on the use of computer
codes
The most recently acquired or tested computer
codes
and data libraries are:
| Identification |
Name |
Description |
NEA-1747/01
|
MONTE-CARLO-WS-2005
|
Proceedings of Monte Carlo
Criticality Calculations & TRIPOLI-IV Workshops 2005
|
| IAEA0867/04 |
ZZ IRDF-2002 |
640-Group Cross-Section Library and Spectra for Dosimetry
Calculation in ENDF-6 Format (New)
|
| USCD1232/01 |
ODEPACK |
Initial Value Problems of
Ordinary Differential Equation System (New) |
USCD1227/01
|
LSODA |
Ordinary Differential Equation Solver for Stiff or
Non-Stiff System (New)
|
USCD1228/01
|
LSODAR |
Ordinary Differential Equation Solver for Stiff or
Non-Stiff System with
Rootfinding (New) |
USCD1224/01
|
LSODI |
Implicit Ordinary Differential Equations System Either
Dense or Banded Matrices (New) |
USCD1225/01
|
LSODIS |
Implicit Ordinary Differential Equations System Sparse
Matrices (New) |
USCD1229/01
|
LSODES |
Ordinary Differential Equations System Sparse Matrices (New) |
USCD1223/01
|
LSODE |
1st Order Stiff or Non-Stiff Ordinary Differential
Equations System Initial Value Problems (New) |
USCD1230/01
|
LSODKR |
Stiff Ordinary Differential Equations (ODE) System Solver
with Krylov Iteration with Rootfinding (New) |
USCD1226/01
|
LSOIBT |
Implicit Ordinary Differential Equations System Block
Tridiagonal Matrices (New) |
USCD1231/01
|
LSODPK |
Ordinary Differential Equations Solver for Stiff and
Nonstiff System with Krylov Corrector Iteration (New) |
IAEA1412/02
|
ZZ-MINSKACT |
Evaluated neutron reaction
data for Th-232, Pa, U, Np, Pu, Am and Cm isotopes (New) |
NEA-1746/01
|
ZZ-PBMR-400 |
OECD/NEA PBMR Coupled
Neutronics/Thermal Hydraulics Transient Benchmark - The PBMR-400 Core
Design (New) |
IAEA1395/05
|
XNWLUP3.0 |
Graphical user interface
to plot WIMS-D library multigroup cross sections (Revised Edition) |
NEA-1735/03
|
CARL2.1 |
radiotoxicity, activity, dose and decay power
calculations for spent fuel (Revised
Edition) |
NEA-1552/19
|
SINBAD-TEPC-FLUKA
|
TEPC-FLUKA Comparison
(New) |
NEA-1517/72
|
SINBAD-RFNC-PHOTONS
|
Photon Leakage Spectra
from Al, Ti, Fe, Cu, Zr, Pb, U238 Spheres (New)
|
NEA-1525/10
|
PENELOPE2005
|
A Code System for Monte-Carlo Simulation
of Electron and Photon Transport (Tested)
|
NEA-1640/08
|
ZZ-BWRTT
|
BWR Turbine Trip Transient Benchmark Based
on Peach-Bottom 2 (Revised Edition)
|
| NEA-1739/01 |
IRPhE/AVR
|
High Temperature Reactor Experience,
Archival Documentation (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) was updated with new experiments and contains now 851 cases
(1 June 2005).
- The Shielding Benchmark Experiments Database (SINBAD) includes now 36 Reactor Shielding-26 Fusion Neutronics
Shielding-, and 13 Accelerator Shielding-Experiments. (last update: 27
September 2005). A
new version will be
issued 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 and 2006:
- Workshop on Evaluation
of Uncertainties in Relation to Severe Accidents and Level 2
Probabilistic Safety
Analysis, Cadarache (France), 7-9 November 2005
- 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. For more information
please
contact: Enrico Sartori
- 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
- 15-17 September 2006
Workshop on Use of Monte Carlo Techniques for Design and Analysis of
Radiation Detectors, University of Coimbra, Coimbra, Portugal
- 25-29 September 2006
9th Information Exchange Meeting on Actinide and Fission Product
Partitioning and Transmutation
Nimes, Frances
Contact: Federico Mompean
- 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 (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,
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
- Meetings Sponsored by the Nuclear
Science Committee & Data Bank
- 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
- 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/
- 18-22 September 2005
2005 Nuclear Criticality Safety Topical - Integrating
Criticality Safety
into the Resurgence of Nuclear Power
Knoxville, TN, USA
http://meetingsandconferences.com/ncsd2005/
- 19-23 September 2005
Sixth International Conference on WWER Fuel
Performance, Modelling and
Experimental Support
Albena, Bulgaria

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/html/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
2007
- 15-18 April 2007
SNA-2007 + M&C-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 or Enrico Sartori
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