OECD/NEA Data Bank
Computer Program Service (CPS) E-Newsletter
No. 5, September 2001
most recently acquired computer codes and data are:
Multicomponent 2- & 3-D Reactive Flows with Fuel Sprays
generator and graphical display of geometry & results for determinsitic
Structure Safety Analysis for Nuclear Power Plants
ORIGEN-S Cross-Section Libraries for CANDU Reactor Fuels
Multi-Step Monte Carlo Burnup Code System.
Interpolable ENDF/B-VI.7 data for 8 temperatures
Resonance Spectrum Calculation system
& Mechanical Behaviour of LWR Fuel Rods
& Isotopics in PWR BWR Fuel Rods
3-D x-y-z Nodal Diffusion Code for Vector Computers
Transient Analysis of Reactor Cores
for Analysis of Fast Reactor Fuel Cycles.
multigroup diffusion/transport theory nodal& finite difference
solver variational method
||80 and 24
groups cross-section library in MATXS format based on JEF-2.2 for
||175 n -
42 gamma groups cross sections in MATXS format based on ENDF/B-VI.5for
energy cross section library from ENDF/B-VI.5 for MCNP-4A, -4B 300K,
for ORIGEN2 code based on JENDL-3.2
For more details see weekly updated list (on
useful links about codes has recently been expanded.
on the Nuclear Data Service can be found in http://www.oecd-nea.org/html/dbdata/
Note to recipients of the Nuclear Program Abstracts on CD-ROM
Recently we sent to you the computer program abstracts on CD-ROM, a searchable
ACCESS database for identifying computer codes carrying out specific tasks.
We have discovered that our CD-ROM reproduction unit had one faulty CD cutter
out of 4, thus 25% of the CD-ROMs we have distributed do not work. If you
have one of these and you wish to receive a working one please send an e-mail
Integral Experiments Data Bases
The CSNI Code
Validation Matrix Separate
Effects Test Data have been extended in the following way :
CD-ROMs No.8 and 10
of the set have been modified accordingly and are available to the recipients
of the CCVM database.
Training Courses, Workshops & Tutorials (co-organised with RSICC)
The MCNP introductory training
course was held from 10-14 September 2001 at Stuttgart, Germany and was
attended by 23 participants.
2001, the following training courses, tutorials or code user group
meetings are proposed :
TRIPOLI-3.5 (Monte Carlo) training course (in French), (2-4 October, 2001 at NEA,
For 2002 we plan
tentatively in addition the following training courses/workshops
(electron-photon transport) workshop
with tutorial, (5-7 November 2001, NEA, Paris),
4.4A - Criticality, Shielding, Source Term (tentative)
on deterministic radiation transport codes (tentatively early 2002).
The intention is to present also recently developed tools for modelling
3D problems, including automated mesh generation, (X-Y-Z), (R-THETA-Z)
and the visualisation of the corresponding results to facilitate interpretation
and for improved documentation. Methods for 3D Sensitivity Analysis
/ Uncertainty Analysis should also be demonstrated. The Data Bank Executive
Group has strongly recommended the development of such tools.
Workshop on Computing
Radiation Dosimetry with embedded training course on MCNPX
- Monte Carlo Code System for Multiparticle & High Energy Applications
Instituto Tecnologico e Nuclear (ITN), Sacavem,
Lisbon, Portugal 22-28 June 2002.
During the weekend of 22-23 June a series of tutorial
lectures will be held followed by a daily tutorial lecture delivered by
a senior expert, on a subject related to the MCNPX module(s) being taught
The MCNPX specific training will be delivered during
Introductory or Advanced Course
(electron-photon transport) workshop with tutorial, (Spring 2002, RSICC,
Oak Ridge, Tennessee, USA)
Cross-Section Processing System (summer-autumn 2002), Issy-les-Moulineaux,
The proposed courses, tutorials etc. will be held
depending on user interest and participation.
Other Meetings / Conferences
News from the OECD Nuclear Energy Agency (NEA)
The latest issue of the NEA online bulletin.