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OECD/NEA Data Bank
Computer Program Service (CPS) E-Newsletter
No. 16, December 2003
Computer Program Service
of the OECD/NEA Data Bank
Content:
- New computer codes & related information
- Integral Experiments
- 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
.
- 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.
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