Computer Programs
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New computer programs acquisitions and updates in the last year

24-APR-23 NEA-1001 KORIGEN, Isotope Inventory, Radiation Heat from PWR Burnup
(Tested)
24-APR-23 NEA-1929 POSY, Power system model for system costs evaluation - Will be released soon
(Tested)
24-APR-23 NEA-1923 SERPENT V2.2.X, 3-D continuous-energy Monte Carlo reactor physics burnup calculation, lattice physics applications
(Tested)
31-JAN-23 IAEA1379 PREPRO2021, Data Preparation and Management, Subsidiary Calculations (ENDF Format)
(Tested)
25-JAN-23 CCC-0767 SWORD 7.0, SoftWare for Optimization of Radiation Detectors
(Arrived)
25-JAN-23 CCC-0638 TART2022, 3D Coupled Neutron-Photon Combinatorial Geometry, Time Dependent, Monte Carlo Transport Code
(Arrived)
18-JAN-23 NEA-1864 GEF 2021/1.1, Code for Simulation of Nuclear Fission Process
(Tested)
13-DEC-22 NEA-1930 MELGENBRIEF, A Code To Extract Control Volume Information From MELGEN Output File of The MELCOR code
(Arrived)
13-DEC-22 NEA-1922 MEXTRA 1.1, A Code To Extract Numerical Value From MAAP Code Output Files
(Arrived)
09-DEC-22 PSR-0317 TRANSX-2.15, Neutron Gamma Particle Transport Tables from MATXS Format Cross-Sections
(Arrived)
30-NOV-22 IAEA1441 ZZ POINT-2021, ENDF/B-VIII.0 Temperature Dependent Cross Section Library
(Arrived)
03-NOV-22 PSR-0610 GADRAS-DRF-18.8.13, Gamma Detector Response and Analysis Software-Detector Response Function
(Arrived)
25-OCT-22 CCC-0858 TMAP7, Tritium Migration Analysis Program
(Arrived)
20-OCT-22 CCC-0783 RASCAL 4.3, Radiological Assessment Systems for Consequence AnaLysis
(Arrived)
16-SEP-22 NEA-1927 ZZ AMPXJEFF3.1.1UPM, AMPX-formatted Neutron Cross Section Library and Covariances based on JEFF-3.1.1
(Arrived)
16-SEP-22 NEA-1928 ZZ AMPXJEFF3.3-UPM, AMPX-formatted Neutron Cross Section Library and Covariances based on JEFF-3.3
(Arrived)
25-AUG-22 NEA-1916 FINPSA TRAINING 2.2.0.1 -R-, a PSA model in consisting of event trees, fault trees, and cut sets
(Tested)
06-JUL-22 DLC-0125 FIREDATA, Nuclear Power Plant Fire Database
(Arrived)
28-JUN-22 NEA-0914 REFIT-2009, Multilevel Resonance Parameter Least Square Fit of N Transmission, Capture, Fission & Self Indication Data
(Tested)
16-JUN-22 NEA-1926 N-THERMALISATION, Notes on the scattering of thermal neutrons
(Arrived)
15-JUN-22 NEA-1925 TCOFF, Thermodynamic Char. of Fuel Debris and Fission Products based on Scenario Analysis of Severe Accident Progression
(Arrived)