nea-1839 |
ACAB-2008, ACtivation ABacus Code |
nea-1638 |
ANITA-IEAF, Isotope Inventories from Intermediate Energy Neutron Irradiation for Fusion Applications |
ccc-0657 |
BETA-S 6, Multi-Group Beta-Ray Spectra |
ccc-0459 |
BOLD/VENTURE-4, Reactor Analysis System with Sensitivity and Burnup |
nea-1735 |
CARL 2.3, radiotoxicity, activity, dose and decay power calculations for spent fuel |
ests1071 |
CECP(BWR) CECP(PWR), Decommissioning Costs for PWR and BWR |
ccc-0544 |
CEPXS ONELD, 1-D Coupled Electron Photon MultiGroup System |
ccc-0837 |
CEPXS, Coupled Electron-Photon Cross Section |
ccc-0604 |
CHAINS-PC, Decay Chain Atomic Densities |
ccc-0755 |
CINDER 1.05, Actinide Transmutation Calculations Code |
nesc0313 |
CINDER, Depletion and Decay Chain Calculation for Fission Products in Thermal Reactors |
nesc0387 |
CITATION, 3-D MultiGroup Diffusion with 1st Order Perturbation and Criticality Search |
ccc-0643 |
CITATION-LDI2, 2-D MultiGroup Diffusion, Perturbation, Criticality Search, for PC |
iaea0883 |
CLUB, Cell Calculation PF Candu PWR Fuel Clusters |
nesc0873 |
COAST-4, Design and Cost of Tokamak Fusion Reactors |
psr-0614 |
COBRA-SFS 6.0, Thermal-Hydraulic Analysis of Multi-Assembly Spent Fuel Storage and Transportation Systems |
ests0135 |
COBRA-SFS CYCLE3, Thermal Hydraulic Analysis of Spent Fuel Casks |
nesc0498 |
CONCEPT-5, Cost and Economics Analysis for Nuclear Fuel or Fossil Fuel Power Plant |
iaea1226 |
CORD-2, PWR Core Design and Fuel Management |
iaea0873 |
CRITIC, In-Core Fuel Management for CANDU PWR |
nea-1892 |
CUMYIELD.MT, cumulative yields calculations of radioactive decay isotopes considering decay chain |
ccc-0640 |
DCHAIN, Isotope Buildup and Isotope Decay by 1 Point Approximation |
nea-1603 |
DCHAIN-SP 2001, Code System for Analyzing Decay and Build-up Characteristics of Spallation Products |
nea-1893 |
DECAYHEAT.MT, decay heat calculations from radioactive isotopes |
nea-1887 |
DESAE, develop prospective nuclear energy scenarios in a regional and global scale |
psr-0531 |
EEDB, The Energy Economic Data Base |
nea-1683 |
ERANOS 2.3N, Modular code and data system for fast reactor neutronics analyses |
nea-0617 |
FAPMAN-IC, LWR Fuel Cost Analysis with Program ORSIM Interface |
nea-1080 |
FEMAXI-6, Thermal and Mechanical Behaviour of LWR Fuel Rods |
nea-1901 |
FINIX 1.19.12, thermal and mechanical behaviour of a nuclear fuel rod during steady-state and transient conditions |
nea-0897 |
FISP-6, Fission Products Inventory and Energy Release in Irradiated Fuel |
nea-0706 |
FISPIN, Isotope Buildup and Isotope Decay for Actinides, Fission Products, Structure Materials |
nesc0301 |
FREVAP-6, Metal Fission Products Release from HTGR Fuel Elements |
nesc0576 |
GEM-NESC, Fuel Cycle Cost and Economics for Thermal Reactor, Present Worth Analysis |
nea-1894 |
INVENTDYN.MT, calculates the dynamics of the amount of isotope and its daughter nuclides with time stamps |
nea-0624 |
JOSHUA, Neutronics, Hydraulics, Burnup, Refuelling of LWR |
nea-0288 |
KERBREK, Fuel Cycle Cost Analysis for Power Reactor |
nea-1001 |
KORIGEN, Isotope Inventory, Radiation Heat from PWR Burnup |
nea-0441 |
KPD, Time-Dependent Fuel Cycle Cost Calculation for Various Reactor Types |
ccc-0631 |
LWRARC-1.0, PWR and BWR Spent Fuel Decay Heat Generator |
nea-1643 |
MCB1C, Monte-Carlo Continuous Energy Burnup Code |
iaea0889 |
MCRAC/RBI, In Core Fuel Management, Program of PFMP System |
psr-0455 |
MONTEBURNS 2.0, An Automated, Multi-Step Monte Carlo Burnup Code System |
nea-1845 |
MURE v2 - SMURE, MCNP Utility for Reactor Evolution: couples Monte-Carlo transport with fuel burnup calculations |
iaea1411 |
NAAPRO, Neutron Activation Analysis Prognosis and Optimization code |
nesc0683 |
NUFUEL, Conditions for Power Production, U Fuel, Pu Recycle and Reprocessing |
nesc0588 |
ORCOST-2, PWR, BWR, HTGR, Fossil Fuel Power Plant Cost and Economics |
nea-1324 |
OREST, LWR Burnup Simulation Using Program HAMMER and ORIGEN |
ccc-0371 |
ORIGEN-2.2, Isotope Generation and Depletion Code Matrix Exponential Method |
ccc-0702 |
ORIGEN-ARP 2.00, Isotope Generation and Depletion Code System-Matrix Exponential Method with GUI and Graphics Capability |
nea-0622 |
ORIGEN-JR, Radiation Source and Nuclide Transmutation with In-Core Burnup |
nea-1880 |
ORIP-XXI, isotope transmutation simulations |
nea-1339 |
PEPIN, Methodology for Computing Concentrations, Activities, Gamma-Ray Spectra, and Residual Heat from Fission Products. |
nea-1663 |
PLUTON, Isotope Generation and Depletion in Highly Irradiated LWR Fuel Rods |
nea-1929 |
POSY, Power system model for system costs evaluation - Will be released soon |
ccc-0708 |
REBUS-PC 1.4, Code System for Analysis of Research Reactor Fuel Cycles |
ccc-0653 |
REBUS3/VARIANT8.0, Code System for Analysis of Fast Reactor Fuel Cycles |
nesc1065 |
REFCO83, Nuclear Fuel Cycle Cost Economics Using Discounted Cash Flow Analysis |
nea-1231 |
REFREP, Near-Field Model for Spent Fuel Repository |
nea-1840 |
SERPENT 1.1.7, 3-D continuous-energy Monte Carlo reactor physics burnup calculation, lattice physics applications |
nea-1923 |
SERPENT V2.2.X, 3-D continuous-energy Monte Carlo reactor physics burnup calculation, lattice physics applications |
nea-1767 |
SMAFS, Steady-state analysis Model for Advanced Fuelcycle Schemes |
nea-0450 |
SOTHIS, PWR Fuel Cycle Equilibrium Cost Evaluation |
nea-0374 |
SPES, Fuel Cycle Optimization for LWR |
nea-1151 |
SUSD, Sensitivity and Uncertainty in Neutron Transport and Detector Response |
nea-1628 |
SUSD3D, 1-, 2-, 3-Dimensional Cross Section Sensitivity and Uncertainty Code |
iaea1214 |
TRIGAC, Flux and Power Distribution and Burnup for TRIGA Reactor |
nea-0415 |
TRITON, 3-D Multi-Region Neutron Diffusion Burnup with Criticality Search |
iaea0884 |
TRIVENI, 3-D Fuel Management for PHWR CANDU |
ccc-0654 |
VENTURE-PC 1.1, Reactor Analysis System with Sensitivity and Burnup |
nea-1856 |
VESTA 2.1&AURORA1.0, Monte Carlo depletion interface code and AURORA 1.0.0, Depletion analysis tool |
iaea0871 |
VPI-NECM, Nuclear Engineering Program Collection for College Training |
nea-0655 |
VSOP, Neutron Spectra, 2-D Flux Synthesis, Fuel Management, Thermohydraulics Calculation |
iaea1440 |
VSOP99-11, Neutron Spectra, 2-D Flux Synthesis, Fuel Management, Thermohydraulics Calculation |
nea-1882 |
XSUN-2023, Windows interface environment for transport and sensitivity-uncertainty software TRANSX-2, PARTISN and SUSD3D |