Nuclear Energy Agency Online Bulletin

Covers new material for December 2001 and January 2002

The monthly bulletin only lists new and updated material. It is distributed by e-mail to registered users of the Nuclear Energy Agency's Online Services and is available online at The bulletin is sent monthly by e-mail to subscribers. It is best received in HTML if you have a mail reader that can display mail in HTML. If you are not already a subscriber, use the registration form to subscribe. An online archive of previous editions is available.

The February bulletin covers the following items:

New publications
Nuclear safety
Nuclear science
Data Bank

New publications

NEA News
ISBN 92-64-19108-9, ISSN 1605-9581.
2002 including two issues. 40 pages.

Disponible également en français :
AEN Infos
ISBN 92-64-29108-3, ISSN 1605-959X.
2002 comportant deux numéros. 40 pages.

Nuclear Law Bulletin No. 68 + Supplement
ISBN 92-64-19110-0, ISSN 0304-341X.
2002 including two issues. Bulletin 98 pages - Supplement 74 pages.

Disponible également en français :
Bulletin de droit nucléaire n° 68 + supplément
ISBN 92-64-29110-5, ISSN 0304-3428.
2002 comportant deux numéros. Bulletin 104 pages - Supplément 77 pages.

Trends in the Nuclear Fuel Cycle
ISBN 92-64-19664-1. 160 pages.

Version française à paraître.

PENELOPE - A Code System for Monte Carlo Simulation of Electron and Photon Transport
ISBN 92-64-18475-9. 250 pages (2.6 mb).


Nuclear safety

Most of the nuclear fuel safety criteria in use today were established during the 1960s and early 1970s. The NEA Committee on the Safety of Nuclear Installations (CSNI) was given a mandate to review these criteria in the light of "new design" elements, such as new fuel and core design, cladding materials, manufacturing processes, high burn-up, mixed-oxide fuel (MOX), etc. The CSNI Task Force on Fuel Safety Criteria (TFFSC) that was set up to consider these issues included research experts from regulatory bodies and technical support organisations. The TFFSC reviewed 20 criteria in all. Also reviewed were the special problems associated with high burn-up, including the axial offset anomaly and incomplete rod insertion. The TFFSC concluded that the current framework of fuel safety criteria "remains generally applicable" to the new fuel designs, but numbers in individual criteria may have to change in accordance with the particular fuel and core design features. The complete text of the TFFSC's report, "Nuclear Fuel Safety Criteria Technical Review" is available online.

Regular features

Nuclear science

The Nuclear Science Committee (NSC) is organising a third workshop on the "Utilisation and Reliability of High Power Proton Accelerators". The workshop will be held in Santa Fe, New Mexico, USA on 12-16 May 2002. More information (including online registration) is available at

The 7th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation will be held in Jeju, Korea on 14-16 October 2002. Participants in this meeting are encouraged to submit abstracts before March 1st. Further information is available at

Data Bank

Nuclear data services

The JEFF Working Party on Nuclear Data Evaluation, Processing and Benchmarking will hold its regular meetings on 24-26 April 2002 in Aix-en-Provence, France. More information (including online registration) is available at

The Data Bank and the Radiation Safety Information Computational Center (RSICC) are organising a training course on the analysis code SAMMY at NEA headquarters on 18-22 February 2002. More information (including online registration) is available at

Computer program services

The Data Bank regularly organises hands-on training courses for widely used computer codes that are in the public domain. The latest training course covered "PENELOPE, a Code System for Monte Carlo Simulation of Electron and Photon Transport". This code is now being used by an increasing number of radiation physicists. Further information about the PENELOPE code is available at

A page listing all new programs in the last 12 months can be found at

New software packages available from the Data Bank:

18-JAN-2002 IAEA1378 INDOSE V2.1.1, Internal Dosimetry Code using Biokinetics Models (Now tested)
18-JAN-2002 NEA-1166 MCVIEW, 3-D Radiation View Factor by Monte-Carlo Method (Now tested)
18-JAN-2002 NEA-1209 DWBA98, DWBA with non local potential (Now tested)
18-JAN-2002 USCD1208 CHECKER, ENDF/B format Check (Now tested)
18-JAN-2002 USCD1210 GETMAT, ENDF/B material retrieval (Now tested)
18-JAN-2002 USCD1214 LISTEF, ENDF/B data file summary list (Now tested)
18-JAN-2002 USCD1216 PSYCHE, ENDF/B data consistency check in ENDF format (Now tested)
18-JAN-2002 USCD1218 STANEF, ENDF/B bookeeping operations for ENDF format files (Now tested)
18-JAN-2002 USCD1217 SETMDC, CDC,IBM,DEC preprocessor for CHECKER, FIZCON, INTER, etc. source codes (Now tested)
18-JAN-2002 USCD1215 PLOTEF, ENDF/B data plot (Now tested)
18-JAN-2002 USCD1212 INTER, ENDF/B thermal cross-sections, resonance integrals, g-factors calculation (Now tested)
18-JAN-2002 USCD1209 FIZCON, ENDF/B cross-sections redundancy check (Now tested)
18-JAN-2002 NEA-1651 ZZ-MCLIB-E6, Continuous energy cross section library from ENDF/B-VI.5 for MCNP-4A,-4B, 300K, 600K, 900K (Now tested)
18-JAN-2002 NEA-1650 ZZ-KAFAX-F22, 80 and 24 groups cross-section library in MATXS format based on JEF-2.2 for fast reactors (Now tested)
18-JAN-2002 NEA-1649 ZZ-KASHIL-E6, 175 n, 42 gamma groups cross sections in MATXS format based on ENDF/B-VI.5 for shielding applications (Now tested)
16-JAN-2002 NEA-1564 EASY,European N Activation System (Now tested)
15-JAN-2002 NEA-1210 ZZ HATCHES-14, Database for Radio Chemical Modelling (Now tested)
11-JAN-2002 NEA-1517 SINBAD-REACTOR, Shielding Benchmark Experiments (Arrived)
11-JAN-2002 NEA-1553 SINBAD-FUSION, Neutronics Benchmark Experiments (Arrived)
10-JAN-2002 NEA-1525 PENELOPE2001, A Code System for Monte Carlo Simulation of Electron and Photon Transport (Arrived)
17-DEC-2001 NEA-1640 ZZ-BWRTT, BWR Turbine Trip Transient Benchmark based on Peach-Bottom 2 (Arrived)

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An online archive of previous editions is available here.