catalog | categories | new | search | index |

New acquisitions and updates in the last year

21-DEC-11 NEA-1553 SINBAD FUSION, Neutronics Benchmark Experiments
(Arrived)
21-DEC-11 NEA-1517 SINBAD REACTOR, Shielding Benchmark Experiments.
(Arrived)
16-DEC-11 NEA-1564 EASY-2010, European Neutron Activation System
(Arrived)
09-DEC-11 DLC-0245 ZZ VITAMINB7/BUGLEB7, Broad-Grp, Fine-Grp, Coupled N/Gamma Cross-Sec Lib derived from ENDF/B-VII.0 Nuclear Data
(Arrived)
08-DEC-11 CCC-0786 RESRAD 6.5, Residual Radioactive Material Guideline Implementation
(Arrived)
02-DEC-11 NEA-1869 ZZ VITJEFF311.BOLIB, JEFF-3.1.1 Multi-Group Coupled (199n + 42gamma) X-Sec Lib in AMPX Fmt for Nuclear Fission Applic.
(Tested)
02-DEC-11 NEA-1778 IFPE/IFA-514/565, LWR MOX Fuel Irradiation Tests - HBWR Irradiation with the Instrument Rig, IFA-514/565 (JAEA) 6 rods
(Arrived)
01-DEC-11 NEA-1693 ZZ V1000CT-1&2, VVER-1000 Main Coolant Pump Switching-on, Coolant Mixing Tests, Main Steam-Line Break Benchmarks
(Arrived)
16-NOV-11 NEA-1849 ZZ PSBT, NUPEC PWR Sub-channel Bundle Tests Benchmark
(Arrived)
14-NOV-11 CCC-0784 DIF3D10.0, Variational Nodal Methods, Finite Difference Methods to Solve N diffusion & Transport Theory Problems
(Arrived)
14-NOV-11 CCC-0254 ANISN-ORNL, 1-D Neutron Transport & Gamma Transport in Slab, Cylindrical, Spherical Geometry with Anisotropic Scattering
(Arrived)
14-NOV-11 CCC-0768 NRCDOSE72 1.2.1, Evaluation of Routine Radioactive Effluents from Nuclear Power Plants with Windows Interface
(Arrived)
14-NOV-11 CCC-0759 TITAN 1.24, A Three-Dimensional Deterministic Radiation Transport Code System
(Arrived)
09-NOV-11 NEA-1769 ZZ UAM-LWR, Uncertainty Analysis in Modelling, Coupled Multi-physics and Multi-scale LWR analysis
(Tested)
08-NOV-11 NEA-1848 ZZ KALININ3, KALININ-3 Coolant Transient Benchmark
(Tested)
28-OCT-11 NEA-1868 ZZ PIXE2010, Proton/alpha ionization (K,L,M shell) tabulated cross section library
(Tested)
27-OCT-11 NEA-1846 FSKY4C, Gamma Ray Skyshine Analysis Code
(Tested)
27-OCT-11 NEA-0914 REFIT, Multilevel Resonance Parameter Least Square Fit of Neutron Transmission, Capture, Fission & Self Indication Data
(Tested)
26-OCT-11 NEA-1864 GEF, code for simulation of nuclear fission process
(Arrived)
13-OCT-11 IAEA1430 ZZ POINT-2009, a Temperature Dependent ENDF/B-VII.0 Cross Section Library
(Tested)
13-OCT-11 USCD1239 VENTEASY, Criticality search for a desired Keffective by adjusting dimensions, nuclide concentrations, or buckling
(Tested)
13-OCT-11 NEA-0829 SCAT-2, Cross Sections and Angular Distributions for Spherical Nuclei by Optical Model
SCAT-2B, Spherical, Optical Model Cross Sections Calculation for N, P, D, T, He3, He4, Heavy Ions
(Tested)
13-OCT-11 DLC-0247 ZZ POINT2011, linearly interpolable ENDF/B-VII.1 Beta2 cross section library for 13 temperatures
(Tested)
12-OCT-11 NEA-1863 IFPE/BN-MOX-M510/D10, Belgonucleaire Beznau-1 PWR irradiated MOX Fuel Rod M510/D10
(Arrived)
12-OCT-11 NEA-1860 IFPE/IFA-519.9, Three PWR rods irradiated to 90 MWd/kg UO2
(Arrived)
12-OCT-11 NEA-1861 IFPE/IFA-629.1, The Re-irradiation of MIMAS-MOX Fuel in IFA-629.1
(Arrived)
12-OCT-11 NEA-1862 IFPE/IFA-650.1 & .2, LOCA testing at Halden, Two experiments, IFA-650 series
(Arrived)
12-OCT-11 NEA-1766 IFPE/KOLA-3-MIR-RAMP, KOLA-3 MIR test temperature during ramp, FGR and pressure at EOL, Bu up to 55 MWd/kgUO2
(Arrived)
12-OCT-11 NEA-1557 IFPE/SUPER-RAMP, PCI Failure Threshold for PWR and BWR Fuels
(Arrived)
16-SEP-11 NEA-1833 FLUKA2011.2, Monte Carlo general purpose tool for calculations of particle transport and interactions with matter
(Arrived)
05-SEP-11 PSR-0405 SAPHIRE 7.27, Systems Analysis Programs for Hands-On Integrated Reliability Evaluations
(Arrived)
01-SEP-11 NEA-1686 ENTREE 1.4.0, BWR Core Simulation System for Space and Time Dependent Coupled Phenomena
(Tested)
31-AUG-11 IAEA1314 RELABEL2010, Labels FORTRAN Statements in ENDF Format Processing Programs
(Tested)
31-AUG-11 IAEA0854 SIGMA1-2010, Doppler Broadening ENDF Format Linear-Linear. Interpolated Point Cross Section
(Tested)
31-AUG-11 IAEA0932 VIRGIN2010, Calculates Uncollided Neutron Flux and Neutron Reactions from Transmission in ENDF Format
(Tested)
31-AUG-11 IAEA1283 SIXPAK2010, ENDF Format Double Differential Cross Section Converter to Single Differential Format
(Tested)
31-AUG-11 IAEA1433 SPECTRA2010, Convert model and general tabulation to linearized spectra (MF=5)
(Tested)
31-AUG-11 IAEA0848 RECENT2010, Reconstruction of Cross Sections Data from Resonance Parameters
(Tested)
30-AUG-11 IAEA1380 ACTIVATE2010, Activation Cross Section by Combining Cross Section and Multiplier (ENDF Format)
(Tested)
30-AUG-11 IAEA1321 COMPLOT2010, Compare ENDF/B Plots of Reaction Data
(Tested)
30-AUG-11 IAEA1307 CONVERT2010, FORTRAN Program Converter for Different Computers
(Tested)
30-AUG-11 IAEA1308 DICTIN2010, Reaction Index Generated for ENDF Format
(Tested)
30-AUG-11 IAEA1322 EVALPLOT2010, ENDF Plots Cross Section, Angular Distribution and Energy Distribution
(Tested)
30-AUG-11 IAEA1309 FIXUP2010, ENDF Format Redundant Cross-Sections Check
(Tested)
30-AUG-11 IAEA0849 GROUPIE2010, Bondarenko Self-Shielded Cross Sections from ENDF/B
(Tested)
30-AUG-11 IAEA1310 LEGEND2010, Angular Distribution Table Calculations in ENDF Format
(Tested)
30-AUG-11 IAEA1311 LINEAR2010, Linear-Linear Interpolation of ENDF Format Cross-Sections
(Tested)
30-AUG-11 IAEA1312 MERGER2010, Merges ENDF/B Data by Material Number or Identifier
(Tested)
30-AUG-11 IAEA1313 MIXER2010, Cross Sections Calculations for a Composite Mixture of ENDF Format Material
(Tested)
30-AUG-11 IAEA1379 PREPRO2010, Data Preparation and Management, Subsidiary Calculations (ENDF Format)
(Tested)
26-AUG-11 CCC-0781 VARSKIN 4 V4.0.0, Dose Calculation for Skin Contamination, with Sadde Input Generator
(Arrived)
24-AUG-11 NEA-1867 RAPID, RAdial power and burnup Prediction by following fissile Isotope Distribution in the pellet
(Tested)
19-AUG-11 CCC-0785 SCALE 6.1, Modular system for criticality, shielding, source term, fuel depletion/decay, inventories, reactor physics
(Arrived)
21-JUL-11 NEA-1865 KICHE 1.3, Kinetics of Iodine Chemistry in the Containment of LWRs under Severe Accident Conditions
(Tested)
21-JUL-11 NEA-1838 JASMINE V.3, Steam explosion simulation
(Tested)
28-JUN-11 NEA-1765 IRPHE2011-HANDBOOK, International Handbook of Evaluated Reactor Physics Benchmark Experiments
(Arrived)
24-JUN-11 NEA-1866 ZZ BUGJEFF311.BOLIB, JEFF-3.1.1 Broad-Group Coupled X Sect Lib. for LWR Shielding & Pressure Vessel Dosimetry Applic.
(Tested)
23-MAY-11 NEA-1525 PENELOPE2011, A Code System for Monte-Carlo Simulation of Electron and Photon Transport
(Tested)
18-MAY-11 NEA-1839 ACAB-2008, ACtivation ABacus Code
(Tested)
18-MAY-11 USCD1234 DRAGON 3.05D, Reactor Cell Calculation System with Burnup
(Tested)
18-MAY-11 IAEA1382 SRNA-2K5, Proton Transport Using 3-D by Monte Carlo Techniques
(Tested)
16-MAY-11 NEA-1080 FEMAXI-6, Thermal and Mechanical Behaviour of LWR Fuel Rods
RODBURN, Power Profiles and Isotopics in PWR, BWR Fuel Rods
(Tested)
15-APR-11 PSR-0563 FEAST-METAL-V.1.0, Fuel Engineering and Structural analysis Tool
(Arrived)
13-APR-11 CCC-0777 COG 11, Multiparticle Monte Carlo Code System for Shielding and Criticality Use
(Arrived)
31-MAR-11 CSNI2017 MCCI-2 PROJECT, Melt Coolability and Concrete Interaction Phase 2 Project
(Arrived)
29-MAR-11 NEA-1857 PHITS-2.24, Particle and Heavy Ion Transport code System
(Tested)
28-MAR-11 CCC-0295 ELGATL, Calculation of Energy Spectra from Coupled Electron-Photon Slowing Down
(Arrived)
22-MAR-11 USCD1240 VIM_NC, VIM color syntax for Nuclear Codes: NJOY, DRAGON, PARTISN, TORT, MONK, and MCNP
(Tested)
16-MAR-11 IAEA0970 STOPOW, Stopping Power of Fast Ions in Matter
(Tested)
16-MAR-11 IAEA1287 SHIELD, Monte-Carlo Code for Simulating Interaction of High Energy Hadrons with Complex Macroscopic Targets
(Tested)
15-MAR-11 USCD1238 ALICE2011, Particle Spectra from HMS precompound Nucleus Decay
(Tested)
07-MAR-11 CCC-0767 SWORD 3.2, SoftWare for Optimization of Radiation Detectors
(Arrived)
03-MAR-11 NEA-1856 VESTA 2.0.3, Monte Carlo depletion interface code
(Arrived)
03-MAR-11 NEA-1210 ZZ HATCHES-19, Database for radiochemical modelling
(Tested)
23-FEB-11 CCC-0761 RSAC-7.2, Gamma doses, inhalation and ingestion doses, fission products inventory after fission products release
(Arrived)
23-FEB-11 CCC-0644 HOTSPOT 2.07.1, Field Evaluation of Radiation Release from Nuclear Accident
(Arrived)
10-FEB-11 NEA-1486 ICSBEP-2010, International Criticality Safety Benchmark Experiment Handbook
(Arrived)