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.
by keywords can be made
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.