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.
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).
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: www.oecd-nea.org/nsd-09-03.html.
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: www.oecd-nea.org/nsd/workshops/debris/.
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: www.oecd-nea.org/nsd/workshops/thicket-2004/index.html.
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: http://sna-2003.cea.fr.
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: www.ans.org/pubs/journals/nse/vol/145.html; more information about the ICSBEP is available at: www.oecd-nea.org/science/wpncs/icsbep/.
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/
|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)|
Instructions on retrieving material from the NEA may be found at www.oecd-nea.org/. Please note that scientific database access is only available to residents of OECD/NEA Data Bank member countries.
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 www.oecd-nea.org/general/mnb/. Registration is free; please use the sign-on form at www.oecd-nea.org/general/register/. An online archive of previous editions is available at www.oecd-nea.org/general/mnb/.
Should you wish to unsubscribe, please use this link.