Nuclear Energy Agency Online Bulletin

Covers new material for July & August 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. To request the HTML version of the bulletin, please e-mail with the subject "HTML Bulletin" and give your full name. If you are not already a subscriber, use the registration form to subscribe. An online archive of previous editions is available.

The September bulletin covers the following items:

New publications
Nuclear development
Nuclear safety
Nuclear science
Data Bank

New publications

Advanced Reactors with Innovative Fuels
Workshop Proceedings, Chester, United Kingdom, 22-24 October 2001
516 pages.

The Use of Thermodynamic Databases in Performance Assessment
Workshop Proceedings, Bacelona, Spain, 29-30 May 2001
220 pages.

Uranium 2001: Resources, Production and Demand
352 pages.

Catalogue of Publications 2002-2003
Bilingual, 68 pages. Paper copies available on request.

Innovative Nuclear Reactor Development: Opportunities for International Co-operation
94 pages (661 kb).

Nuclear Energy and the Kyoto Protocol
ISBN 92-64-18486-4. 52 pages (235 kb).

Disponible également en français :
L'énergie nucléaire et le Protocole de Kyoto
ISBN 92-64-28486-9. 54 pages (216 kb).

Executive summary also available in Japanese:
Nuclear Energy and the Kyoto Protocol
6 pages (600 kb).

Nuclear development

The World Summit on Sustainable Development held in Johannesburg, South Africa on 26 August - 4 September 2002 targeted energy as one of the five focal points for discussion. More information on the NEA's participation in the summit is available at

Nuclear safety

The CSNI Working Group on Risk Assessment (WGRISK) recently issued the report "The use and development of probabilistic safety assessment in NEA member countries" [NEA/CSNI/R(2002)18]. This report describes the current status of member country PSA programmes.

Regular features

Nuclear science

A new edition of the "International Handbook of Nuclear Criticality Safety Benchmark Experiments" has just been published. This new edition includes new and revised experimental evaluations as well as an enhanced version of the Database for the International Handbook of Evaluated Criticality Safety Benchmark Experiments (DICE). Available free in CD-ROM format, the publication can be obtained by completing the order form at

Data Bank

Computer program services

A page listing all new programs in the last 12 months can be found at Detailed news concerning the computer program service is available at:


New software packages available from the Data Bank

  05-SEP-2002 PSR-0158 SAMMY, Resonance Parameters from Experimental Neutron Cross Section by R-Matrix Theory (Arrived)
  05-SEP-2002 CCC-0702 ORIGEN-ARP 2.00, Isotope Generation and Depletion Code System-Matrix Exponential Method with GUI and Graphics Capability (Arrived)
  30-AUG-2002 NEA-1643 MCB1C, Monte-Carlo Continuous Energy Burnup Code (Now tested)
  30-AUG-2002 NEA-1667 ZZ-MCB-JEF2.2, MCB Continuous-Energy Neutron Cross Section Libraries for Temperatures from 300 to 1800 K. (Now tested)
  30-AUG-2002 NEA-1669 ZZ-MCB-ENDF/B6.8, MCB Continuous-Energy Neutron Cross Section Libraries for Temperatures from 300 to 1800 K. (Now tested)
  30-AUG-2002 NEA-1668 ZZ-MCB-EAF99, MCB Continuous-Energy Neutron Cross Section Libraries for Temperatures from 300 to 1800 K. (Now tested)
  30-AUG-2002 NEA-1670 ZZ-MCB-JENDL-3.2, MCB Continuous-Energy Neutron Cross Section Libraries for Temperatures from 300 to 1800 K. (Now tested)
  30-AUG-2002 NEA-1424 ZZ FSXJ32, MCNP nuclear data library based on JENDL-3.2 (Now tested)
  30-AUG-2002 DLC-0200 ZZ MCNPDATA, Standard Neutron, Photon and Electron Data Libraries for MCNP-4C and MCNP4C2 (Now tested)
  29-AUG-2002 USCD1205 PCNUDAT-PCNULIB, Nuclear Properties Data Base and Retrieval System (Arrived)
  26-AUG-2002 NEA-1675 PPICA, Power Plant Investment Cost Analysis (Now tested)
  26-AUG-2002 CCC-0553 RASCAL 3.0.3, Radiological Doses from Accidental Release to Atmosphere (Arrived)
  23-AUG-2002 IAEA1384 NKE, Nuclide Explorer tool for retrieving interactively detailed data on radionuclides properties (Arrived)
  22-AUG-2002 USCD1208 CHECKR, ENDF/B Format Check (Arrived)
  22-AUG-2002 USCD1209 FIZCON, ENDF/B Cross-Sections Redundancy Check (Arrived)
  22-AUG-2002 USCD1212 INTER, ENDF/B Thermal Cross-Sections, Resonance Integrals, G-Factors Calculation (Arrived)
  22-AUG-2002 USCD1210 GETMAT, ENDF/B Material Retrieval (Arrived)
  22-AUG-2002 USCD1215 PLOTEF, ENDF/B Data Plot (Arrived)
  22-AUG-2002 USCD1217 SETMDC: Preprocessor for CHECKR, FIZCON, INTER, etc. ENDF Utility source codes (Arrived)
  22-AUG-2002 USCD1218 STANEF, ENDF/B Bookeeping Operations for ENDF Format Files (Arrived)
  22-AUG-2002 USCD1216 PSYCHE, ENDF/B Data Consistency Check in ENDF Format (Arrived)
  22-AUG-2002 USCD1214 LISTEF, ENDF/B Data File Summary List (Arrived)
  19-AUG-2002 IAEA1395 XNWLUP1.1, Graphical user interface to plot WIMS-D library multigroup cross sections (Now tested)
  13-AUG-2002 NEA-1657 ANL-BPB, Argonne National Laboratory Code Center Benchmark Problem Book (Now tested)
  21-JUL-2002 DLC-0208 ZZ-ELAST2, Database of Cross Sections for the Elastic Scattering of Electrons and Positrons by Atoms (Now tested)
  19-JUL-2002 IAEA1202 EQUIVA, Few-Group Diffusion Parameter for PWR Reflector Region by 1-D Transport Calculation (Now tested)
  18-JUL-2002 IAEA1175 GRAP, Gamma-Ray Level-Scheme Assignment (Now tested)
  18-JUL-2002 NEA-1451 MUTIL, Asymmetry Factor of Mott Cross-Sections for Electron, Positron Scattering (Now tested)
  18-JUL-2002 NEA-1422 NESKA, Electron and Positron Scattering from Point Nuclei (Now tested)
  18-JUL-2002 NEA-1239 SFERXS, Photoabsorption, Coherent, Incoherent Scattering Cross-Sections Function for Shielding (Now tested)
  11-JUL-2002 DLC-0187 ZZ HILO86R, 66 Neutron, 22 Gamma Group Cross-Section for 400 MeV Neutron, 20 MeV Gamma (Now tested)
  11-JUL-2002 DLC-0210 ZZ-CANDULIB-AECL, Burnup-Dependent ORIGEN-S Cross-Section Libraries for CANDU Reactor Fuels (Now tested)
  11-JUL-2002 CCC-0705 MCNPX 2.3.0, Monte Carlo Code System for Multiparticle and High Energy Applications (Arrived)
  11-JUL-2002 NEA-1674 ZZ-TH232-UNIBO, Th-232 cross section data for MCNP (Arrived)
  11-JUL-2002 DLC-0205 ZZ MCNPXDATA, Neutron, Photon, and Electron Data Libraries for MCNPX (Arrived)
  09-JUL-2002 DLC-0211 ZZ-UTXS6, MCNP Continuous-Energy Neutron Cross Section Libraries for Temperatures from 300 to 1365 K. (Now tested)

Please note that scientific database access is only available to residents of OECD/NEA Data Bank member countries.

Should you wish to unsubscribe, please use this link.

An online archive of previous editions is available here.