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OECD/NEA
Data Bank
Computer
Program Service (CPS) E-Newsletter
No. 10,
September 2002
Computer
Program Service
of the OECD/NEA Data Bank Computer Codes
The
most recently acquired and / or tested computer codes and data are:
| NEA-1657 |
ANL-BPB |
Argonne
National Laboratory Code Center Benchmark Problem Book (Arrived and tested) |
| IAEA-1202 |
EQUIVA |
Few-Group
Diffusion Parameter for PWR Reflector Region by 1-D Transport Calculation
(Now tested) |
| IAEA-1175 |
GRAP |
Gamma-Ray
Level-Scheme Assignment (Now tested) |
| IAEA-0886 |
INTERTRAN-II |
INTERTRAN-I
and INTERTRAN-II, Radiation Exposure from Vehicle Transport of Radioactive
Material (Arrived and tested) |
| NEA-1451 |
MUTIL |
Asymmetry
Factor of Mott Cross-Sections for Electron, Positron Scattering (Now tested) |
| NEA-1422 |
NESKA |
Electron
and Positron Scattering from Point Nuclei (Now tested) |
| IAEA-1384 |
NKE |
Nuclide
Explorer tool for retrieving interactively detailed data on radionuclides
properties (Arrived and tested) |
| CCC-0702 |
ORIGEN-ARP
2.00 |
Isotope
Generation and Depletion Code System-Matrix Exponential Method with GUI
and Graphics Capability (Arrived) |
| USCD-1205 |
PCNULIB |
PCNUDAT-PCNULIB,
Nuclear Properties Data Base and Retrieval System (Arrived and tested) |
| NEA-1675 |
PPICA |
Power
Plant Investment Cost Analysis (Arrived and tested) |
| CCC-0553 |
RASCAL
3.0.3 |
Radiological
Doses from Accidental Release to Atmosphere (Arrived) |
| PSR-0158 |
SAMMY-M6B |
Resonance
Parameters from Experimental Neutron Cross Section by R-Matrix Theory (Arrived) |
| NEA-1239 |
SFERXS |
Photoabsorption,
Coherent, Incoherent Scattering Cross-Sections Function for Shielding (Now
tested) |
| IAEA-1395 |
XNWLUP1.1 |
Graphical
user interface to plot WIMS-D library multigroup cross sections (Arrived
and tested) |
| USCD-1208 |
CHECKR-6.13 |
ENDF/B
Format Check (Arrived) |
| USCD-1209 |
FIZCON-6.13 |
ENDF/B
Cross-Sections Redundancy Check (Arrived) |
| USCD-1210 |
GETMAT-6.13 |
ENDF/B
Material Retrieval (Arrived) |
| USCD-1212 |
INTER-6.13 |
ENDF/B
Thermal Cross-Sections, Resonance Integrals, G-Factors Calculation (Arrived) |
| USCD-1214 |
LISTEF-6.13 |
ENDF/B
Data File Summary List (Arrived) |
| USCD-1215 |
PLOTEF-6.13 |
ENDF/B
Data Plot (Arrived) |
| USCD-1216 |
PSYCHE-6.13 |
ENDF/B
Data Consistency Check in ENDF Format (Arrived) |
| USCD-1217 |
SETMDC-6.13 |
Preprocessor
for CHECKR, FIZCON, INTER, etc. ENDF Utility source codes (Arrived) |
| USCD-1218 |
STANEF-6.13 |
ENDF/B
Bookkeeping Operations for ENDF Format Files (Arrived) |
| DLC-0210 |
ZZ-CANDULIB-AECL |
Burnup-Dependent
ORIGEN-S Cross-Section Libraries for CANDU Reactor Fuels (Now tested) |
| DLC-0208 |
ZZ-ELAST2 |
Database
of Cross Sections for the Elastic Scattering of Electrons and Positrons
by Atoms (Now tested) |
| DLC-0187 |
ZZ-HILO86R |
66
Neutron, 22 Gamma Group Cross-Section for 400 MeV Neutron, 20 MeV Gamma
(Now tested) |
| NEA-1643 |
MCB1C |
Monte-Carlo
Continuous Energy Burnup Code (Arrived and tested) |
| DLC-0200 |
ZZ-MCB-DLC200 |
ZZ
MCNPDATA, Standard Neutron, Photon and Electron Data Libraries for MCNP-4C
and MCB1C (Arrived and tested) |
| NEA-1668 |
ZZ-MCB-EAF99 |
MCB
Continuous-Energy Neutron Cross Section Libraries for Temperatures from
300 to 1800 K (Arrived and tested) |
| NEA-1669 |
ZZ-MCB-ENDF/B-6.8 |
MCB
Continuous-Energy Neutron Cross Section Libraries for Temperatures from
300 to 1800 K (Arrived and tested) |
| NEA-1667 |
ZZ-MCB-JEF2.2 |
MCB
Continuous-Energy Neutron Cross Section Libraries for Temperatures from
300 to 1800 K (Arrived and tested) |
| NEA-1670 |
ZZ-MCB-JENDL-3.2 |
MCB
Continuous-Energy Neutron Cross Section Libraries for Temperatures from
300 to 1800 K (Arrived and tested) |
| DLC-0212 |
ZZ-POINT2000 |
Linearly
Interpolable ENDF/B-VI.7 Data for 8 Temperatures (Now tested) |
| DLC-0192 |
ZZ-POINT97 |
Temperature-Dependent
ENDF/B-6 Cross-Sections at 8 Temperature Between 0K and 2100K (Now tested) |
Note:
All computer code documentation has now been scanned and will be distributed
exclusively on the CD-ROM in electronic format with the program package.
No paper copies of manuals will be provided as from now.
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).
-
The
International Fuel Performance Experiments Database (IFPE) was recently enriched with new experiments and some evaluations
of the experiments were revised.
Training
Courses & Tutorials:
Recently completed Workshops / Courses
-
Workshop
on Computing Radiation Dosimetry (CRD-2002) with embedded training
course on MCNPX
-
Monte Carlo Code System for Multiparticle & High Energy Applications,
was held at the Instituto Tecnologico e Nuclear (ITN), Sacavem, Lisbon,
Portugal 22-28 June 2002.
The
MCNPX specific training was held from 24-28 June. The Workshop proceedings
will be printed in the autumn 2002. More details are provided in the CRD-2002
Web page
-
MCNP
- Introductory
Course including MCNP5 Features, from 9-13 September 2002 at
the University of Stuttgart, Germany
For
2002
the following training courses/workshops are planned:
-
MCNPX
Training course 18-22 November 2002 at SCK.CEN Club-House Salon 2,
Mol, Belgium
-
Note
that the SCALE Physor 2002 Workshop in Korea was cancelled
For
2003
the following training courses/workshops are planned:
-
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)
-
Workshop
on deterministic radiation (DT) transport codes (tentatively
early 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-2001
(electron-photon transport) training course / tutorial, (March or April
2003, NEA, Paris), (see previous workshop
report)
-
KENO
/ SCALE Training Courses 2003, April / May 2003 in Paris France
-
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 (letter by the author)
-
MCNP5
Training Course(1 or 2), date and place not yet firmly decided (France
/ UK / Germany)
-
AMPX-2000
Cross-Section Processing System (summer, autumn 2003), Issy-les-Moulineaux,
France. (proposed programme)
-
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
The
proposed courses, tutorials etc. will be held depending on user interest
and participation.
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)
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