New acquisitions and updates in the last year
| 13-APR-12 | USCD1236 | ZZ SCALE6.0/COVA-44G, 44-group cross section covariance matrix library extracted from SCALE6.0 ZZ SCALE5.1/COVA-44G, 44-group cross section covariance matrix library extracted from SCALE5.1 (Tested) |
| 26-MAR-12 | DLC-0245 | ZZ VITAMINB7/BUGLEB7, Broad-Grp, Fine-Grp, Coupled N/Gamma Cross-Sec Lib derived from ENDF/B-VII.0 Nuclear Data (Arrived) |
| 21-MAR-12 | NEA-1864 | GEF, Code for Simulation of Nuclear Fission Process (Arrived) |
| 16-MAR-12 | NEA-1688 | SACALC3, Calculates the average solid angle subtended by a volume (Arrived) |
| 14-MAR-12 | CCC-0767 | SWORD 4.0, SoftWare for Optimization of Radiation Detectors (Arrived) |
| 14-MAR-12 | NEA-1552 | SINBAD ACCELERATOR, Shielding Benchmark Experiments (Arrived) |
| 13-MAR-12 | IAEA1434 | U-SHIELDER, Estimates Shielding Thickness of Depleted Uranium for Photons from 0.5 to 10 MeV (Arrived) |
| 09-MAR-12 | CSNI2020 | SETH-2, OECD/NEA SESAR Thermal-hydraulics Project (Arrived) |
| 08-MAR-12 | CSNI2019 | SCIP, OECD/NEA Studsvik Cladding Integrity Project (Arrived) |
| 06-MAR-12 | CSNI2018 | BIP PROJECT, OECD/NEA Behaviour of Iodine Project (Arrived) |
| 05-MAR-12 | NEA-1833 | FLUKA2011.2, Monte Carlo general purpose tool for calculations of particle transport and interactions with matter (Arrived) |
| 01-MAR-12 | NEA-1553 | SINBAD FUSION, Neutronics Benchmark Experiments (Arrived) |
| 01-MAR-12 | NEA-1517 | SINBAD REACTOR, Shielding Benchmark Experiments. (Arrived) |
| 29-FEB-12 | NEA-1278 | CALENDF-2010, Pointwise, Multigroup Neutron Cross-Sections and Probability Tables from ENDF/B Evaluations (Arrived) |
| 16-DEC-11 | NEA-1564 | EASY-2010, European Neutron Activation System (Arrived) |
| 08-DEC-11 | CCC-0786 | RESRAD 6.5, Residual Radioactive Material Guideline Implementation (Arrived) |
| 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) |
| 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) |
| 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 (Arrived) |
| 08-NOV-11 | NEA-1848 | ZZ KALININ3, KALININ-3 Coolant Transient Benchmark (Arrived) |
| 28-OCT-11 | NEA-1868 | ZZ PIXE2010, Proton/Alpha Ionization (K,L,M shell) Tabulated Cross-Section Library (Tested) |
| 27-OCT-11 | NEA-0914 | REFIT, Multilevel Resonance Parameter Least Square Fit of Neutron Transmission, Capture, Fission & Self Indication Data (Tested) |
| 27-OCT-11 | NEA-1846 | FSKY4C, Gamma Ray Skyshine Analysis Code (Tested) |
| 13-OCT-11 | DLC-0247 | ZZ POINT2011, Linearly Interpolable ENDF/B-VII.1 Beta2 Cross-Section Library for 13 Temperatures (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 | 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) |
| 12-OCT-11 | NEA-1862 | IFPE/IFA-650.1 & .2, LOCA testing at Halden, Two experiments, IFA-650 series (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-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-1860 | IFPE/IFA-519.9, Three PWR rods irradiated to 90 MWd/kg UO2 (Arrived) |
| 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-1557 | IFPE/SUPER-RAMP, PCI Failure Threshold for PWR and BWR Fuels (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 | IAEA0932 | VIRGIN2010, Calculates Uncollided Neutron Flux and Neutron Reactions from Transmission in ENDF Format (Tested) |
| 31-AUG-11 | IAEA1433 | SPECTRA2010, Convert model and general tabulation to linearized spectra (MF=5) (Tested) |
| 31-AUG-11 | IAEA1283 | SIXPAK2010, ENDF Format Double Differential Cross Section Converter to Single Differential Format (Tested) |
| 31-AUG-11 | IAEA0854 | SIGMA1-2010, Doppler Broadening ENDF Format Linear-Linear. Interpolated Point Cross Section (Tested) |
| 31-AUG-11 | IAEA1314 | RELABEL2010, Labels FORTRAN Statements in ENDF Format Processing Programs (Tested) |
| 31-AUG-11 | IAEA0848 | RECENT2010, Reconstruction of Cross Sections Data from Resonance Parameters (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 | 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 | 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) |
| 30-AUG-11 | IAEA1310 | LEGEND2010, Angular Distribution Table Calculations in ENDF Format (Tested) |
| 30-AUG-11 | IAEA0849 | GROUPIE2010, Bondarenko Self-Shielded Cross Sections from ENDF/B (Tested) |
| 30-AUG-11 | IAEA1309 | FIXUP2010, ENDF Format Redundant Cross-Sections Check (Tested) |
| 30-AUG-11 | IAEA1322 | EVALPLOT2010, ENDF Plots Cross Section, Angular Distribution and Energy Distribution (Tested) |
| 30-AUG-11 | IAEA1308 | DICTIN2010, Reaction Index Generated for 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-1838 | JASMINE V.3, Steam explosion simulation (Tested) |
| 21-JUL-11 | NEA-1865 | KICHE 1.3, Kinetics of Iodine Chemistry in the Containment of LWRs under Severe Accident Conditions (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) |