Computer Programs
catalog | categories | new | search |

Catalog of Programs in Category D

D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

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