OECD/NEA Data Bank

Computer Program Service (CPS) E-Newsletter

No. 16, December 2003

Computer Program Service of the OECD/NEA Data Bank
Content:
  1. New computer codes & related information
  2. Integral Experiments
  3. Workshops, Training Courses & Tutorials, Meetings

The most recently acquired or tested computer codes and data libraries are:


Identification Name Description
NEA-1687/04
IRPHE/B&W-SS-LATTICE
IRPHE/B&W-SS-LATTICE, Spectral Shift Reactor Lattice Experiments (Revised Edition)
NEA-1715/01
IRPHE-JAPAN
Reactor Physics Experiments carried out in Japan (New)
NEA-1660/04
IRPHE-SNEAK
IRPHE-SNEAK, KFK SNEAK Fast Reactor Experiments, Primary Documentation (Revised Edition)
NEA-1713/01
IRPHE/RRR-SEG
Reactor Physics Experiments from Fast-Thermal Coupled Facility RRR-SEG, Rossendorf (New)
NEA-1714/01
IRPHE/STEK
Reactor Physics Experiments from Fast-Thermal Coupled Facility STEK, Petten (New)
NEA-1694/02
SATIF/CYCLO-RADSAFE
Health Physics and Radiological Safety of Cyclotrons 10-250 MeV (Revised Edition)
NEA-1716/01 TRIPOLI-4.3.2 Coupled Neutron, Photon, Electron, Positron 3-D, Time Dependent Monte-Carlo, Transport Calculation (New)
NEA-1640/07 ZZ-BWRTT BWR Turbine Trip Transient Benchmark Based on Peach-Bottom 2 (Revised Edition)
NEA-1554/05 ZZ-PWR-MSLB PWR Main Steam-Line Break Benchmarks, Coupled Neutronics Thermal-Hydraulics (Final Edition)
NEA-1424/04 ZZ-FSXLIBJ33 MCNP nuclear data library based on JENDL-3.3 (Tested)
NEA-1705/01
IFPE/CAGR-UOX-SWELL Fuel swelling Data Obtained from the AGR/Halden Ramp Test Programme (New)
NEA-1710/01 IFPE/MT4-MT6A-LOCA Large-break LOCA in-reactor fuel bundle materials tests at NRU (New)
NEA-1707/01 ZZ-MATXSLIBJ33 JENDL-3.3 based,175 N-42 photon groups (VITAMIN-J) MATXS lib. for discrete ordinates multi-group (Tested)
NEA-1699/01 ZZ-VITJEF22.BOLIB JEF-2.2 Multigr Coupled (199n + 42gamma) X-Section Lib. in AMPX Fmt for Nuclear Fission Applications (New)
NEA-1693/01 ZZ-V1000CT-1 VVER-1000 Main Coolant Pump (MCP) Switching On Benchmark (New)
NEA-1680/02 PASCAL Probabilistic Fracture Mechanics Analysis of Structural Components in Aging LWR (New)
CCC-0547/08 DANTSYS3.0
1-D, 2-D MultiGroup Discrete Ordinate Method Transport
(Tested)
NEA-1711/01 DORTDAT2 Input-Making Support System for a Two-Dimensional SN Code, DORT (New)
NEA-1517/65 SINBAD BALAKOVO-3 VVER-1000 Ex-vessel Neutron Dosimetry Benchmark (Updated)
NEA-1278/03 CALENDF-2002 Pointwise, Multigroup Neutron Cross-Sections and Probability Tables Production from ENDF/B Evaluations (New)
IAEA1409/01 ZZ-POINT-2003 Linearly Interpolable ENDF/B-VI.8 Data for 8 Temperatures (New)
IAEA1407/01 ZZ-RRDF-98 Cross-sections and covariance matrices for 22 neutron induced dosimetry reactions (New)
ESTS1145/02 PCX Interior-Point Linear Programming Solver (New)
NEA-1561/08 CHEMENGL/CHIMISTE Chemical and Physical Properties of Elements (New)
NEA-1570/01 SITE-94 SITE-94, Biosphere Model for SKI Project on the island of Aspro (Tested)
ESTS1169/01 ARCON96 ARCON96, Radioactive Plume Concentration in Reactor Control Rooms (Tested)

Note : All computer codes with documentation are now distributed exclusively in electronic form either on  CD-ROM or via FTP. No paper copies of manuals are provided.

For more details see weekly updated list (on Mondays)

Integral Experiments Data for Model and Code Validation

Compilations and evaluations have been updated concerning the:
  • The latest status of the International Reactor Physics Benchmark Experiments Project is given in IRPhE . Here you can download a summary . Further information can be obtained from Enrico Sartori ( sartori@oecd-nea.org )
  • The International Fuel Performance Experiments Database (IFPE) was recently enriched with new experiments (2 December 2003).
  • The Shielding Benchmark Experiments Database (SINBAD) includes now 33 Reactor Shielding, 21 for Fusion Neutronics Shielding and 5 for Accelerator Shielding Experiments. The October 2003 SINBAD edition contains 10 new experiments.
  • A new Edition of the CCVM (CSNI Code Validation Matrix of Thermo-Hydraulic Codes for LWR LOCA and Transients) is now available .

Workshops, Training Courses & Tutorials completed in 2003:

  • Seminar on Pellet-Clad Interaction (PCI) in Water Reactor Fuels , 8-11 March 2004, Aix-en-Provence, France
  • Tenth International Conference on Radiation Shielding (ICRS-10) with ANS Topical on Radiation Protection & Shielding (RP&S), 9-14 May 2004, Madeira Island, Portugal

News from the OECD Nuclear Energy Agency (NEA)

The latest issue of the NEA on-line bulletin.