
OECD/NEA
Data Bank
Computer
Program Service (CPS) ENewsletter
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:
NEA1657 
ANLBPB 
Argonne
National Laboratory Code Center Benchmark Problem Book (Arrived and tested) 
IAEA1202 
EQUIVA 
FewGroup
Diffusion Parameter for PWR Reflector Region by 1D Transport Calculation
(Now tested) 
IAEA1175 
GRAP 
GammaRay
LevelScheme Assignment (Now tested) 
IAEA0886 
INTERTRANII 
INTERTRANI
and INTERTRANII, Radiation Exposure from Vehicle Transport of Radioactive
Material (Arrived and tested) 
NEA1451 
MUTIL 
Asymmetry
Factor of Mott CrossSections for Electron, Positron Scattering (Now tested) 
NEA1422 
NESKA 
Electron
and Positron Scattering from Point Nuclei (Now tested) 
IAEA1384 
NKE 
Nuclide
Explorer tool for retrieving interactively detailed data on radionuclides
properties (Arrived and tested) 
CCC0702 
ORIGENARP
2.00 
Isotope
Generation and Depletion Code SystemMatrix Exponential Method with GUI
and Graphics Capability (Arrived) 
USCD1205 
PCNULIB 
PCNUDATPCNULIB,
Nuclear Properties Data Base and Retrieval System (Arrived and tested) 
NEA1675 
PPICA 
Power
Plant Investment Cost Analysis (Arrived and tested) 
CCC0553 
RASCAL
3.0.3 
Radiological
Doses from Accidental Release to Atmosphere (Arrived) 
PSR0158 
SAMMYM6B 
Resonance
Parameters from Experimental Neutron Cross Section by RMatrix Theory (Arrived) 
NEA1239 
SFERXS 
Photoabsorption,
Coherent, Incoherent Scattering CrossSections Function for Shielding (Now
tested) 
IAEA1395 
XNWLUP1.1 
Graphical
user interface to plot WIMSD library multigroup cross sections (Arrived
and tested) 
USCD1208 
CHECKR6.13 
ENDF/B
Format Check (Arrived) 
USCD1209 
FIZCON6.13 
ENDF/B
CrossSections Redundancy Check (Arrived) 
USCD1210 
GETMAT6.13 
ENDF/B
Material Retrieval (Arrived) 
USCD1212 
INTER6.13 
ENDF/B
Thermal CrossSections, Resonance Integrals, GFactors Calculation (Arrived) 
USCD1214 
LISTEF6.13 
ENDF/B
Data File Summary List (Arrived) 
USCD1215 
PLOTEF6.13 
ENDF/B
Data Plot (Arrived) 
USCD1216 
PSYCHE6.13 
ENDF/B
Data Consistency Check in ENDF Format (Arrived) 
USCD1217 
SETMDC6.13 
Preprocessor
for CHECKR, FIZCON, INTER, etc. ENDF Utility source codes (Arrived) 
USCD1218 
STANEF6.13 
ENDF/B
Bookkeeping Operations for ENDF Format Files (Arrived) 
DLC0210 
ZZCANDULIBAECL 
BurnupDependent
ORIGENS CrossSection Libraries for CANDU Reactor Fuels (Now tested) 
DLC0208 
ZZELAST2 
Database
of Cross Sections for the Elastic Scattering of Electrons and Positrons
by Atoms (Now tested) 
DLC0187 
ZZHILO86R 
66
Neutron, 22 Gamma Group CrossSection for 400 MeV Neutron, 20 MeV Gamma
(Now tested) 
NEA1643 
MCB1C 
MonteCarlo
Continuous Energy Burnup Code (Arrived and tested) 
DLC0200 
ZZMCBDLC200 
ZZ
MCNPDATA, Standard Neutron, Photon and Electron Data Libraries for MCNP4C
and MCB1C (Arrived and tested) 
NEA1668 
ZZMCBEAF99 
MCB
ContinuousEnergy Neutron Cross Section Libraries for Temperatures from
300 to 1800 K (Arrived and tested) 
NEA1669 
ZZMCBENDF/B6.8 
MCB
ContinuousEnergy Neutron Cross Section Libraries for Temperatures from
300 to 1800 K (Arrived and tested) 
NEA1667 
ZZMCBJEF2.2 
MCB
ContinuousEnergy Neutron Cross Section Libraries for Temperatures from
300 to 1800 K (Arrived and tested) 
NEA1670 
ZZMCBJENDL3.2 
MCB
ContinuousEnergy Neutron Cross Section Libraries for Temperatures from
300 to 1800 K (Arrived and tested) 
DLC0212 
ZZPOINT2000 
Linearly
Interpolable ENDF/BVI.7 Data for 8 Temperatures (Now tested) 
DLC0192 
ZZPOINT97 
TemperatureDependent
ENDF/B6 CrossSections 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 CDROM 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 (CRD2002) 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 2228 June 2002.
The
MCNPX specific training was held from 2428 June. The Workshop proceedings
will be printed in the autumn 2002. More details are provided in the CRD2002
Web page

MCNP
 Introductory
Course including MCNP5 Features, from 913 September 2002 at
the University of Stuttgart, Germany
For
2002
the following training courses/workshops are planned:

MCNPX
Training course 1822 November 2002 at SCK.CEN ClubHouse 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 (electronphoton transport)',
to be held in Salou (Tarragona) from 810 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, (XYZ), (RTHETAZ) 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.

PENELOPE2001
(electronphoton 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 neutroninduced crosssection data
for extracting values and covariances for resonance parameters), May 1216,
2003, Knoxville, TN, USA (letter by the author)

MCNP5
Training Course(1 or 2), date and place not yet firmly decided (France
/ UK / Germany)

AMPX2000
CrossSection Processing System (summer, autumn 2003), IssylesMoulineaux,
France. (proposed programme)

TOUGH
Symposium , Lawrence Berkeley National Laboratory (LBNL), 57
May May 57A symposium on applications and enhancements of TOUGH
(A GeneralPurpose Numerical Simulator for Multiphase Fluid and Heat Flow)
with oral and poster presentations. Proceedings on CDROM will be available
at the Symposium.
Contact:
Stefan Finsterle, George J. Moridis, Curtis M. Oldenburg, YuShu Wu LBL,
Email: 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)
The
latest
issue of the NEA online bulletin.
