Publications on sale can be ordered at the OECD bookshop: www.oecd.org/scripts/publications/bookshop/redirect.asp.
on the Chemical Thermodynamics of Uranium, Neptunium, Plutonium, Americium
ISBN 0-444-51401-5. Price: 260, US$260. 964 pages.
Free publications are available at www.oecd-nea.org/pub/webpubs/. Paper copies may be requested by sending an e-mail to email@example.com.
Events and Processes Evaluation Catalogue for Argillaceous Media
ISBN 92-64-02148-5. 379 pages (1.5 mb).
Electricity Generation: What Are the External Costs?
ISBN 92-64-02153-1. 82 pages (439 kb).
Management in the Medium Term
A Review by the OECD/NEA Working Party on the Physics of Plutonium Fuels and Innovative Fuel Cycles (WPPR)
ISBN 92-64-02151-5. 72 pages (596 kb).
Water Reactor Main Steam Line Break (MSLB) Benchmark
Volume IV: Results of Phase III on Coupled Core-plant Transient Modelling
ISBN 92-64-02152-3. 183 pages (2.7 mb).
If you would like to be informed about updates to the NEA website - as they are made, or on a daily or weekly basis - a new alert service is now available. With the help of specialised software, the NEA Rich Site Summary (RSS) feed provides a list of headlines, a short description and a link to the updated page or report. Windows users can download the free software FeedReader to access the NEA RSS feed. If you already have the necessary software installed, the NEA RSS feed is available at: www.oecd-nea.org/general/press/nea.rss. More information is available at: www.oecd-nea.org/general/press/rss.html.
The Information System on Occupational Exposures (ISOE) is a unique worldwide programme to review, promote and co-ordinate international co-operative undertakings for the radiological protection of workers at nuclear power plants. It also serves as a forum for discussing occupational exposure management issues and is the repository for the worlds largest database on occupational exposure from nuclear power plants.
The ISOE Steering Group recently conducted an in-depth evaluation of the goals of the Information System. The goals of this evaluation were, inter alia, to: clearly define the ISOE's objectives; analyse ISOE participants' needs and define targets; and identify ways to enhance the ISOE's use and visibility. The evaluation's findings will be implemented during 2004. More information is available at: www.oecd-nea.org/jointproj/isoe.html.
The Forum on Stakeholder Confidence (FSC) held its fourth interactive workshop in Brussels, Belgium on 18-21 November 2003. The Belgian workshop considered stakeholder issues in the context of local partnerships for the long-term management of low-level, short-lived radioactive waste. More information is available at: www.oecd-nea.org/general/mnb/2003/03-11-rwm.html.
Participants in the Joint Evaluated Fission and Fusion File (JEFF) project on nuclear data evaluation, processing and benchmarking met in Paris, France on 17-19 November 2003. New evaluation work has been performed for Fe-58, I-127, I-129, W-184, and for Pb, Bi and Ti isotopes. A new recommendation for delayed neutron data was also produced. The JEFF-3.0 activation library in ENDF-6 format is available on request from Ali Nouri (firstname.lastname@example.org). Recently the JEFF project benchmarking activities have focused on the under-prediction of reactivity for light water reactor lattices. This subject is currently under discussion in an NEA electronic forum at www.oecd-nea.org/lists/ueval.html.
The Seventh International Conference on Nuclear Criticality Safety was held in Tokai-mura, Japan on 20-24 October 2003. Most papers presented at the conference focused on describing experimental data, evaluating experimental programs and applying the results to code validation. Research into criticality excursion analysis (revisiting past accidents, modelling experimental programmes) has increased in many countries. This is almost certainly in response to the 1999 Tokai-mura criticality accident. There is also substantial work being done on code development issues, particularly with Monte Carlo methods. The other topics covered during the conference included the application of general criticality safety methodologies to process facilities, burn-up credit and nuclear data.
The Working Party on Nuclear Criticality Safety and some of the associated
expert groups held their annual meetings in Tokyo, Japan on 15-17 October
2003. More information is available at: www.oecd-nea.org/general/mnb/2003/03-11-nsc.html.
The fifth volume in the NEA chemical thermodynamics series, Update
on the Chemical Thermodynamics of Uranium, Neptunium, Plutonium, Americium
and Technetium, has just been released. The new volume both updates
and expands the thermodynamic data on inorganic compounds and complexes
of uranium, neptunium, plutonium, americium and technetium covered
in previous volumes. A team of seven internationally recognised experts
spent five years critically reviewing all the scientific literature
containing chemical thermodynamic information for the above-mentioned
systems that have appeared since the publication of the earlier volumes.
The results of these critical reviews, carried out in accordance with
the TDB project guidelines, have been documented in the new volume.
The fifth volume also contains new tables of selected values for formation
and reaction thermodynamic properties and an extensive bibliography.
This review will be a valuable reference source for those working
on nuclear waste management and the nuclear fuel cycle. Forthcoming
reviews will cover selenium, nickel, zirconium and organic ligands.
More information is available at: www.oecd-nea.org/dbtdb/.
A page listing all new programs in the last 12 months can be found at: www.oecd-nea.org/dbprog/cpsnew.html. Detailed news concerning the computer program service is available at: www.oecd-nea.org/dbprog/Newsletter/Whatsnew.htm.
Large-break LOCA in-reactor fuel bundle materials tests at NRU
|20-NOV-2003||NEA-1707|| ZZ MATXSLIBJ33,JENDL-3.3
based,175 N-42 photon groups (VITAMIN-J) MATXS library for discrete
|20-NOV-2003||NEA-1676|| ERRORJ, Multigroup
covariance matrices generation from ENDF/B-6 format
KFK SNEAK Fast Reactor Experiments, Primary Documentation
|13-NOV-2003||NEA-1699|| ZZ VITJEF22.BOLIB,
JEF-2.2 Multigr Coupled (199n + 42gamma) X-Section Lib. in AMPX
Fmt for Nuclear Fission Applications
|07-NOV-2003||NEA-1693|| ZZ V1000CT-1
VVER-1000 Main Coolant Pump (MCP) Switching On Benchmark
|06-NOV-2003||NEA-1680|| PASCAL, Probabilistic
Fracture Mechanics Analysis of Structural Components in Aging
DANTSYS3.0, 1-D, 2-D Multi-Group Discrete Ordinate Method Transport
|04-NOV-2003||NEA-1711|| DORTDAT2, Input-Making
Support System for a Two-Dimensional SN Code, DORT
|04-NOV-2003||NEA-1517|| SINBAD REACTOR,
Shielding Benchmark Experiments
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