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 www.oecd-nea.org/science/wpncs/icsbep.
Data Bank
Computer program services
A page listing all new programs in the last 12 months can be found at www.oecd-nea.org/tools/abstract/new.
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New software packages available from the Data Bank
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05-SEP-2002 |
PSR-0158 |
SAMMY, Resonance Parameters from Experimental Neutron Cross Section by R-Matrix Theory (Arrived) |
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05-SEP-2002 |
CCC-0702 |
ORIGEN-ARP 2.00, Isotope Generation and Depletion Code System-Matrix Exponential Method with GUI and Graphics Capability (Arrived) |
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30-AUG-2002 |
NEA-1643 |
MCB1C, Monte-Carlo Continuous Energy Burnup Code (Now tested) |
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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) |
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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) |
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30-AUG-2002 |
NEA-1668 |
ZZ-MCB-EAF99, MCB Continuous-Energy Neutron Cross Section Libraries for Temperatures from 300 to 1800 K. (Now tested) |
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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) |
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30-AUG-2002 |
NEA-1424 |
ZZ FSXJ32, MCNP nuclear data library based on JENDL-3.2 (Now tested) |
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30-AUG-2002 |
DLC-0200 |
ZZ MCNPDATA, Standard Neutron, Photon and Electron Data Libraries for MCNP-4C and MCNP4C2 (Now tested) |
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29-AUG-2002 |
USCD1205 |
PCNUDAT-PCNULIB, Nuclear Properties Data Base and Retrieval System (Arrived) |
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26-AUG-2002 |
NEA-1675 |
PPICA, Power Plant Investment Cost Analysis (Now tested) |
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26-AUG-2002 |
CCC-0553 |
RASCAL 3.0.3, Radiological Doses from Accidental Release to Atmosphere (Arrived) |
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23-AUG-2002 |
IAEA1384 |
NKE, Nuclide Explorer tool for retrieving interactively detailed data on radionuclides properties (Arrived) |
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22-AUG-2002 |
USCD1208 |
CHECKR, ENDF/B Format Check (Arrived) |
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22-AUG-2002 |
USCD1209 |
FIZCON, ENDF/B Cross-Sections Redundancy Check (Arrived) |
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22-AUG-2002 |
USCD1212 |
INTER, ENDF/B Thermal Cross-Sections, Resonance Integrals, G-Factors Calculation (Arrived) |
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22-AUG-2002 |
USCD1210 |
GETMAT, ENDF/B Material Retrieval (Arrived) |
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22-AUG-2002 |
USCD1215 |
PLOTEF, ENDF/B Data Plot (Arrived) |
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22-AUG-2002 |
USCD1217 |
SETMDC: Preprocessor for CHECKR, FIZCON, INTER, etc. ENDF Utility source codes (Arrived) |
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22-AUG-2002 |
USCD1218 |
STANEF, ENDF/B Bookeeping Operations for ENDF Format Files (Arrived) |
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22-AUG-2002 |
USCD1216 |
PSYCHE, ENDF/B Data Consistency Check in ENDF Format (Arrived) |
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22-AUG-2002 |
USCD1214 |
LISTEF, ENDF/B Data File Summary List (Arrived) |
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19-AUG-2002 |
IAEA1395 |
XNWLUP1.1, Graphical user interface to plot WIMS-D library multigroup cross sections (Now tested) |
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13-AUG-2002 |
NEA-1657 |
ANL-BPB, Argonne National Laboratory Code Center Benchmark Problem Book (Now tested) |
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21-JUL-2002 |
DLC-0208 |
ZZ-ELAST2, Database of Cross Sections for the Elastic Scattering of Electrons and Positrons by Atoms (Now tested) |
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19-JUL-2002 |
IAEA1202 |
EQUIVA, Few-Group Diffusion Parameter for PWR Reflector Region by 1-D Transport Calculation (Now tested) |
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18-JUL-2002 |
IAEA1175 |
GRAP, Gamma-Ray Level-Scheme Assignment (Now tested) |
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18-JUL-2002 |
NEA-1451 |
MUTIL, Asymmetry Factor of Mott Cross-Sections for Electron, Positron Scattering (Now tested) |
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18-JUL-2002 |
NEA-1422 |
NESKA, Electron and Positron Scattering from Point Nuclei (Now tested) |
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18-JUL-2002 |
NEA-1239 |
SFERXS, Photoabsorption, Coherent, Incoherent Scattering Cross-Sections Function for Shielding (Now tested) |
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11-JUL-2002 |
DLC-0187 |
ZZ HILO86R, 66 Neutron, 22 Gamma Group Cross-Section for 400 MeV Neutron, 20 MeV Gamma (Now tested) |
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11-JUL-2002 |
DLC-0210 |
ZZ-CANDULIB-AECL, Burnup-Dependent ORIGEN-S Cross-Section Libraries for CANDU Reactor Fuels (Now tested) |
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11-JUL-2002 |
CCC-0705 |
MCNPX 2.3.0, Monte Carlo Code System for Multiparticle and High Energy Applications (Arrived) |
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11-JUL-2002 |
NEA-1674 |
ZZ-TH232-UNIBO, Th-232 cross section data for MCNP (Arrived) |
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11-JUL-2002 |
DLC-0205 |
ZZ MCNPXDATA, Neutron, Photon, and Electron Data Libraries for MCNPX (Arrived) |
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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.
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An online archive of previous editions is available here.