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OECD/NEA
Data Bank
Computer
Program Service (CPS) E-Newsletter
No. 11,
December 2002
Computer
Program Service
of the OECD/NEA Data Bank
The
most recently acquired computer codes and data are:
| IAEA-1391 |
SHIELDER |
Gamma
shielding calculations of radionuclides emitting photons 0-5 to 10 MeV |
| NEA-1627 |
BOT3P2.0 |
2D/3D,
Mesh Generator and Graphical Display of Geometry and Results for Deterministic
Transport Codes |
| NEA-1678 |
BOT3P3.0 |
3D
Mesh Generator and Graphical Display of Geometry for Deterministic &
Monte Carlo Radiation Transport Codes, Display of Results |
| IAEA-1388 |
FOTELP-PEN |
Photons,
Electrons and Positrons Transport in 3D by Monte Carlo Techniques |
| NEA-1553 |
SINBAD-FNS-V |
Neutron
spectra and dosimetry, gamma-ray spectra and heating from a 25.4 cm cube
of Vanadium irradiated with a D-T neutron source (FNS/JAERI clean benchmark) |
| NEA-1552 |
SINBAD-ROESTI |
Hadron
and low-energy neutron fluences and absorbed doses in the cascades induced
in iron and lead dumps irradiated by high-energy hadron beams |
| CCC-0371 |
ORIGEN-2.2 |
Isotope
Generation and Depletion Code Matrix Exponential Method |
| CCC-0708 |
REBUS-PC
1.4 |
Code
System for Analysis of Research Reactor Fuel Cycles |
| CCC-0661 |
SOURCES-4C |
Calculating
Alpha, N, Fission, Delayed Neutron Sources and Spectra |
| CCC-0654 |
VENTURE-PC
1.1 |
Reactor
Analysis System with Sensitivity and Burnup |
| IAEA1397 |
ZZ-WIMS-D/4LIB |
61,
64, 69, 76 and 79 energy groups WIMS-D/4 libraries |
| NEA-1554 |
ZZ-PWR-MSLB-REV.3 |
PWR
Main Steam-Line Break Benchmarks, Coupled Neutronics Thermal-Hydraulics |
| NEA-1086 |
TRISTAN |
3-D
fixed source radiation transport |
| NEA-0446 |
DELIGHT-7 |
Point
Reactivity Burnup for HTGR Lattice with P1 Neutron Scattering Approximation |
| CCC-0537 |
TRIPOS |
Monte
Carlo Ion Transport Analysis Code |
| CCC-0715 |
MCNPX
2.4.0 |
Monte
Carlo N-Particle Transport Code System for Multiparticle and High Energy
Applications |
| DLC-0205 |
ZZ-MCNPXDATA
2.4.0 |
Neutron,
Photon, Electron, and Proton Data Libraries for MCNPX 2.3.0 or 2.4.0 |
| NEA-1640 |
ZZ-BWRTT |
BWR
Turbine Trip Transient Benchmark Based on Peach-Bottom 2 (Update) |
| NEA-1210 |
ZZ-HATCHES-15 |
Database
for Radio Chemical Modelling |
| ESTS0663 |
CFDLIB99.2* |
Computational
Fluid Dynamics Library |
| NEA-1684 |
IFPE/IFA-534.14 |
Fission
gas release as a function of burnup at high power (52-55 MWd/kg) |
| NEA-1685 |
IFPE/IFA-597.3 |
Centre-line
temperature, fission gas release and clad elongation at high burn-up (60-62
MWd/kg) |
| NEA-1561 |
CHEMENGL/CHIMISTE |
Chemical
and Physical Properties of Elements (Update) |
| IAEA1169 |
EMPIRE-II
2.18 |
Comprehensive
Nuclear Model Code, Nucleons, Ions Induced Cross-Sections |
| NEA-1492 |
NUCLEUS-CHART |
Interactive
Chart of Nuclides (Update) |
| NEA-1687 |
IRPHE/B&W-SS-LATTICE |
Spectral
Shift Reactor Lattice Experiments |
| NEA-1679 |
PVIS-4 |
Pressure
vessel irradiation, source preparation |
| NEA-1406 |
TOPICS-B |
Neutron
and Gamma Cross-Sections Library Handling in FIDO Format |
| NEA-0919 |
SRIM-2003 |
Stopping
Power and Range of Ions in Matter |
| NEA-1603 |
DCHAIN-SP
2001 |
Code
System for Analyzing Decay and Build-up Characteristics of Spallation Products |
| NEA-1676 |
ERRORJ |
Multigroup
covariance matrices generation from ENDF/B-6 format |
| NESC0983 |
EGUN |
Charged
Particle Trajectories in Electromagnetic Focusing System (Update) |
Note:
All computer code documentation has now been scanned and is distributed
exclusively on the CD-ROM in electronic format with the program package.
No paper copies of manuals are provided.
For
more details see weekly
updated list
(on Mondays)
Integral
Experiments Data for Model and Code Validation
Compilations
and evaluations have been updated concerning the :
-
Shielding
Experiments Data Base (SINBAD) at NEADB
or RSICC
-
Work
is in progress on the International Reactor Physics Benchmark Experiments
Project. See IRPhE
. Here you can download a
recent summary (July 2002). Further information can be obtained from
Enrico Sartori (sartori@oecd-nea.org )
-
The
International Fuel Performance Experiments Database (IFPE)
was recently enriched with new experiments and some evaluations of the
experiments were revised.
Workshops,
Training Courses & Tutorials planned for 2003:
-
2nd
International Workshop on 'Advanced
radiation transport simulation with PENELOPE (electron-photon transport)',
to be held in Salou (Tarragona) from 8-10 January 2003.(Penelope User Group
meeting)
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Workshop
on Common Tools for Deterministic Radiation
Transport, for Monte Carlo and Hybrid Codes
(25-26 September 2003 in connection with the conference SNA-2003).
The intention is to present in particular recently developed tools for
modelling 3D problems, including in particular automated mesh generation,
(X-Y-Z), (R-THETA-Z) and the visualisation of the corresponding results
to facilitate interpretation and for improved documentation. Presentation
and discussion of methods and ideas for ensuring that the same models are
used in MC and DT for benchmarking; development of compatible and common
mesh generation and visualisation tools for MC and DT; Methods for 3D Sensitivity
Analysis / Uncertainty Analysis should also be demonstrated. The Data Bank
Executive Group has strongly recommended the development of such tools.
If you are interested in participating, please fill
in the form.
-
PENELOPE-2003
(electron-photon transport) training
course / tutorial, (7-10 July 2003, NEA, Paris), (see previous workshop
report) - here is the registration
form
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KENO
/ SCALE Training Courses 2003, 23-27 June 2003 in Paris France
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SAMMY
Workshop (analysis of experimental neutron-induced cross-section data
for extracting values and covariances for resonance parameters), May 12-16,
2003, Knoxville, TN, USA
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MCNP5
Intermediate/Advanced Level Training Course, 24-28 March 2003, at the
Imperial College, London, England
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MCNP5
Training Course, date and place not yet firmly decided (France)
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TOUGH
Symposium, Lawrence Berkeley National Laboratory (LBNL), 5-7 May May
5-7A symposium on applications and enhancements of TOUGH (A General-Purpose
Numerical Simulator for Multiphase Fluid and Heat Flow) with oral and poster
presentations. Proceedings on CD-ROM will be available at the Symposium.
Contact:
Stefan Finsterle, George J. Moridis, Curtis M. Oldenburg, Yu-Shu Wu LBL,
E-mail: SAFinsterle@lbl.gov
-
MCNPX
training course, date and place to be determined.
-
QUADOS
workshop: Intercomparison
on the Usage of Computational Codes in Radiation Dosimetry, 14
- 16 July 2003, Bologna, Italy, organised by: ENEA and University
of Bologna, co-sponsored by: EURADOS, OECD/NEA, Contact: Gianfranco Gualdrini
guald@bologna.enea.it
The
proposed courses, tutorials etc. will be held depending on user interest
and participation. For more information please contact : sartori@oecd-nea.org
Meetings
Sponsored by the Nuclear Science Committee
Meetings
scheduled for the next two years and of interest to clients of
the Computer Program Service
News
from the OECD Nuclear Energy Agency (NEA)
The
latest
issue of the NEA on-line bulletin.
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