Nuclear Energy Agency Online Bulletin

Covers new material for July and August 2003:

New publications
Nuclear safety
Nuclear science
Data Bank

New publications

Decommissioning Nuclear Power Plants
Policies, Strategies and Costs
ISBN 92-64-10431-3. 104 pages.

Engineered Barrier Systems (EBS) in the Context of the Entire Safety Case
Workshop Proceedings, Oxford, UK, 25-27 September 2002
ISBN 92-64-10354-6. 152 pages.

NEA News (spring | autumn)
ISSN 1605-9581. Two issues from 2003.

Disponible également en français :
AEN Infos (printemps | automne)
ISSN 1605-959X. Deux numéros de 2003.

Nuclear Energy Today
Nuclear Energy Today
ISBN 92-64-10328-7. 112 pages.

Benchmark on Beam Interruptions in an Accelerator-driven System
Final Report on Phase I Calculations
ISBN 92-64-02138-8. 28 pages (878 kb).

Benchmark on Deterministic Transport Calculations Without Spatial Homogenisation
A 2-D/3-D MOX Fuel Assembly Benchmark
ISBN 92-64-02139-6. 152 pages (1.7 mb, plus a CD-ROM).

The French R&D Programme on Deep Geological Disposal of Radioactive Waste
An International Peer Review of the "Dossier 2001 Argile"
ISBN 92-64-02136-1. 80 pages (271 kb).

Disponible également en français :
Programme français de R-D sur le stockage géologique de déchets radioactifs
Revue internationale par des pairs du Dossier 2001 Argile
ISBN 92-64-02137-X. 82 pages (418 ko).

International Evaluation Co-operation
Volume 9: Fission Neutron Spectra of Uranium-235
ISBN 92-64-02134-5. 28 pages (143 kb).

Occupational Exposure Management at Nuclear Power Plants
Third ISOE European Workshop, Portoroz, Slovenia, 17-19 April 2002
ISBN 92-64-02135-3. 356 pages (1.3 mb).

Public Information, Consultation and Involvement in Radioactive Waste Management
An International Overview of Approaches and Experiences
Informer, consulter et impliquer le public dans la gestion des déchets radioactifs
Panorama international des approches et expériences
ISBN 92-64-02128-0. Bilingual. 140 pages (687 kb).

Nuclear safety

Preparations for the launch of a new joint project on Computer-based Control Systems Important to Safety (COMPSIS) have made considerable progress over the summer. The proposed project will build on the work of an earlier task force, which collected operating experience in this area and formed a discussion forum to aid regulatory bodies in the licensing of digital instrumentation and control (I&C) systems. The project is expected to begin during the first half of 2004. More information is available at:

A workshop on the impact of debris on emergency coolant recirculation (organised in collaboration with the US Nuclear Regulatory Commission) will be held in Albuquerque, New Mexico, USA, on 25 February-2 March 2004. The workshop will be in two parts: the first part will be restricted to regulatory organisations, their technical support organisations and national laboratories only; the second part will be open to nuclear power plant (NPP) owners and operators, NPP designers and vendors, industry associations, regulatory organisations and their technical support organisations, national laboratories and public interest representatives. Active participation by utilities in the second part of the workshop is strongly encouraged. More information is available at:

A seminar to transfer competence, knowledge and experience gained through CSNI activities in the field of thermal-hydraulics over the past two decades will be held in Saclay, France on 7-11 June 2004. The seminar is primarily aimed at specialists unfamiliar with CSNI activities and to newcomers in the field. The seminar will be hosted by the Institut de radioprotection et de sûreté nucléaire (IRSN). More information is available at:

Related links

Documents from the Committee on the Safety of Nuclear Installations (CSNI)
Documents from the Committee on Nuclear Regulatory Activities (CNRA)
Forthcoming workshops and seminars

Nuclear science

The NEA is co-organising with the CEA, Cogema, EDF and Framatome ANP a conference on Supercomputing in Nuclear Applications (SNA-2003) to be held in Paris, France on 22-24 September 2003. The main objective of the conference is to promote the practice of supercomputing in a wide variety of scientific domains, but especially in the nuclear field and in addressing "Grand Challenge" problems. The conference will begin with a plenary session on Trends in Supercomputing Applications. Subsequent sessions will include 75 oral and 55 poster presentations given by authors from 25 countries. In parallel to the conference, many nuclear and computer industry companies will be exhibiting their products and services. More information is available at:

The next two editions of Nuclear Science and Engineering, the research journal of the American Nuclear Society, will be devoted to papers on the International Criticality Safety Benchmark Evaluation Project (ICSBEP), administered by the NEA. ICSBEP benchmark models are of particular value to criticality safety analysts and nuclear data evaluators for the validation and verification of neutron transport codes and nuclear cross-section data. The ICSBEP evaluation process has had a positive influence on measurement programmes worldwide. More information about the forthcoming September edition of Nuclear Science and Engineering is available at:; more information about the ICSBEP is available 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:

  28-AUG-2003 PSR-0242 SABRINA, Geometry Plot Program for MCNP (Now tested)
  22-AUG-2003 NEA-1678 BOT3P3.0, 3-D Mesh Generator and Graphical Display of Geometry for Radiation Transport Codes, Display of Results (Now tested)
  22-AUG-2003 NEA-1627 BOT3P2.0 2-D/3-D, Mesh Generator and Graphical Display of Geometry and Results for Deterministic Transport Codes (Now tested)
  21-AUG-2003 NEA-1706 MMRW, Canadian and early British Energy Reports on Nuclear Reactor Theory (1940-1946) (Arrived)
  30-JUL-2003 IAEA1365 ZZ-RIPL, ZZ-RIPL-2, Parameter Library for Nuclear Model Calculations (Arrived)
  30-JUL-2003 NEA-1603 DCHAIN-SP 2001, Code System for Analysing Decay and Build-up Characteristics of Spallation Products (Arrived)
  29-JUL-2003 IAEA1401 ZZ-DROSG-2000, Legendre Coefficient Library for 59 monoenergetic neutron source reactions (Arrived)
  28-JUL-2003 IAEA1402 ENDVER, The ENDF File Verification Support Package (Arrived)
  24-JUL-2003 IAEA0848 RECENT2002, Reconstruction of Cross-Section Data from Resonance Parameters (Arrived)
  24-JUL-2003 IAEA1314 RELABEL2002, Labels FORTRAN Statements in ENDF Format Processing Programs (Arrived)
  24-JUL-2003 IAEA0854 SIGMA1-2002, Doppler Broadening ENDF Format Linear-Linear. Interpolated Point Cross Section (Arrived)
  24-JUL-2003 IAEA1283 SIXPAK2002, ENDF Format Double Differential Cross Section Converter to Single Differential Format (Arrived)
  24-JUL-2003 IAEA1310 LEGEND2002, Angular Distribution Table Calculations in ENDF Format (Now tested)
  24-JUL-2003 IAEA1312 MERGER2002, Merges ENDF/B Data by Material Number or Identifier (Now tested)
  24-JUL-2003 IAEA1309 FIXUP2002, ENDF Format Redundant Cross-Sections Check (Now tested)
  24-JUL-2003 IAEA1379 PREPRO2002, Data Preparation and Management, Subsidiary Calculations (ENDF Format) (Now tested)
  24-JUL-2003 IAEA1321 COMPLOT2002, Compare ENDF/B Plots of Reaction Data (Now tested)
  24-JUL-2003 IAEA1322 EVALPLOT2002, ENDF Plots Cross Section, Angular Distribution and Energy Distribution (Now tested)
  24-JUL-2003 IAEA1307 CONVERT2002, FORTRAN Program Converter for Different Computers (Now tested)
  24-JUL-2003 IAEA0932 VIRGIN2002, Calculates Uncollided Neutron Flux and Neutron Reactions from Transmission in ENDF Format (Now tested)
  24-JUL-2003 IAEA1308 DICTIN2002, Reaction Index Generated for ENDF Format (Now tested)
  24-JUL-2003 IAEA1313 MIXER2002, Cross Sections Calculations for a Composite Mixture of ENDF Format Material (Now tested)
  24-JUL-2003 IAEA1311 LINEAR2002, Linear-Linear Interpolation of ENDF Format Cross-Sections (Now tested)
  24-JUL-2003 IAEA0849 GROUPIE2002, Bondarenko Self-Shielded Cross Sections from ENDF/B (Now tested)
  24-JUL-2003 IAEA1380 ACTIVATE2002, Activation Cross Section by Combining Cross Section and Multiplier (ENDF Fomat) (Now tested)
  23-JUL-2003 NEA-1564 EASY, European Neutron Activation System (Arrived)
  21-JUL-2003 NEA-1525 PENELOPE2003, A Code System for Monte-Carlo Simulation of Electron and Photon Transport (Arrived)
  15-JUL-2003 PSR-0365 MOCUP, MCNP/ORIGEN Coupling Utility Programs (Now tested)
  10-JUL-2003 NEA-1492 NUCLEUS-CHART, Interactive Chart of Nuclides (Now tested)
  07-JUL-2003 NEA-1517 SINBAD REACTOR, Shielding Benchmark Experiments (Now tested)
  01-JUL-2003 NEA-0446 DELIGHT-7, Point Reactivity Burnup for HTGR Lattice with P1 Neutron Scattering Approximation (Now tested)
  01-JUL-2003 NEA-1671 DUCT-III, Design Code for Duct-Streaming Radiations (Now tested)
  01-JUL-2003 NEA-1663 PLUTON, Isotope Generation and Depletion in Highly Irradiated LWR Fuel Rods (Now tested)
  01-JUL-2003 NEA-1086 TRISTAN, 3-D fixed source radiation transport (Now tested)
  01-JUL-2003 IAEA1403 C-SHIELDER, Gamma shielding calculations of radionuclides emitting photons 0.5 to 10 MeV by different concretes (Now tested)
  25-JUN-2003 NEA-1662 IRPHE/JOYO MK-II, JOYO MK-II core management and characteristics database (Arrived)

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