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Catalog of Programs in Category D

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


nesc0325 2-DB, 2-D MultiGroup Diffusion, X-Y, R-Theta, Hexagonal Geometry Fast Reactor, Criticality Search
nesc0567 3-DB, 3-D MultiGroup Diffusion, X-Y-Z, R-Theta-Z, Triangular-Z Geometry, Fast Reactor Burnup
nea-0912 ABLEIT-TRANS, Isotope Concentration and Sensitivities on Cross-Sections Data
nea-1839 ACAB-2008, ACtivation ABacus Code
psr-0190 ADENA, Fission Products Beta Spectra and Gamma Spectra in 19 Group from U235 Pu239 Mixture
nea-0321 ANDROMEDA, 1-D Burnup for Fuel Cycle Analysis of FBR
nea-1638 ANITA-2000, Isotope Inventories from Neutron Irradiation, for Fusion Applications
nea-1343 ANITA-4, Isotope Inventories from Neutron Irradiation, for Fusion Applications
ccc-0519 AUS, Neutron Transport and Gamma Transport System for Fission Reactors and Fusion Reactors
nea-0373 BEST-4, Fuel Cycle and Cost Optimization for Discrete Power Levels
nea-0404 BEST-5, Power Reactor Fuel Cycle Optimization by Bellman Method
ccc-0657 BETA-S, Multi-Group Beta-Ray Spectra
nea-0591 BEVE, Isotope Buildup in LWR Fuel Pin with Self-Shielding in Pellet
nea-0870 BISON, 1-D Burnup and Transport in Slab, Cylindrical, Spherical Geometry
ccc-0459 BOLD/VENTURE-4, Reactor Analysis System with Sensitivity and Burnup
nea-0236 BOLERO, 2 Group Burnup for PWR and BWR in R-Z Geometry with Restart and Recycle
nea-1187 BOREAS, Nuclear and Thermohydraulic LWR Burnup Simulation
nea-1523 BOXER, Fine-flux cross section condensation, 2D few group diffusion and transport burnup calculations
nea-0237 BURNY, 5 Group BWR and PWR Burnup in X-Y Geometry by Diffusion Calculation
nea-0350 BURNY-SQUID, 2-D Burnup of UO2 and Mix UO2 PuO2 Fuel in X-Y or R-Z Geometry
nea-1735 CARL 2.3, radiotoxicity, activity, dose and decay power calculations for spent fuel
ests1071 CECP, Decommissioning Costs for PWR and BWR
ccc-0544 CEPXS ONELD, 1-D Coupled Electron Photon MultiGroup System
ccc-0604 CHAINS-PC, Decay Chain Atomic Densities
nea-0451 CICLON, Neutronics Calculation for PWR Transition Fuel Cycle Management
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
nesc0540 CLOTHO, Mass Flow Data Calculation for Program PACTOLUS
iaea0883 CLUB, Cell Calculation PF Candu PWR Fuel Clusters
nesc0873 COAST-4, Design and Cost of Tokamak Fusion Reactors
ests0135 COBRA-SFS CYCLE3, Thermal Hydraulic Analysis of Spent Fuel Casks
nea-1578 COMRAD96, Nuclear Fuel Burnup and Depletion Calculation System
iaea0928 COMTA, Ceramic Fuel Elements Stress Analysis
nesc0498 CONCEPT-5, Cost and Economics Analysis for Nuclear Fuel or Fossil Fuel Power Plant
nea-0427 CONDOR-3, Local and Spectrum Dependent Burnup with Mesh-Wise Depletion
iaea1226 CORD, PWR Core Design and Fuel Management
nea-0463 CRACKLE, Fast Reactor Pu Fuel Management
iaea0873 CRITIC, In-Core Fuel Management for CANDU PWR
nea-0151 DANCOFF-3, Dancoff Correction for Cylindrical Fuel Rod at H2O Gaps and for Fuel Clusters
ccc-0640 DCHAIN, Isotope Buildup and Isotope Decay by 1 Point Approximation
nea-0664 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-0446 DELIGHT-7, Point Reactivity Burnup for HTGR Lattice with P1 Neutron Scattering Approximation
psr-0523 DEPLETOR Version 2, provides depletion capability to the Purdue Advanced Reactor Core Simulator (PARCS) code
nea-0298 DISCOUNT-G, Nuclear Power Program with Cost Analysis and Pu Production Optimization
nesc0579 DWARF, 1-D Few-Group Neutron Diffusion with Thermal Feedback for Burnup and Xe Oscillation
nea-1683 ERANOS 2.0, Modular code and data system for fast reactor neutronics analyses
nea-0534 EREBUS, Burnup by 2-D MultiGroup Neutron Diffusion with Criticality Search
nea-0341 ERUPT, 2-D 2 Group Fuel Management in R-Z Geometry with Fuel Shuffling
nea-0617 FAPMAN-IC, LWR Fuel Cost Analysis with Program ORSIM Interface
nea-0693 FAPMAN-ORSIM, General Cost Optimization for System of Nuclear Power Plants
nea-1080 FEMAXI-6, Thermal and Mechanical Behaviour of LWR Fuel Rods
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
nea-0235 FLARE-JAERI, 3-D BWR and ATR Simulation
ccc-0603 FPZD, Reactor Burnup by MultiGroup Neutron Diffusion
nesc0301 FREVAP-6, Metal Fission Products Release from HTGR Fuel Elements
nea-0314 FURNACE-J, 2-D Diffusion Burnup for Fast Reactors from JAERI Fast-Set
nesc0223 GAD-2, Fuel Cycle Depletion Calculation with Partial Refueling and Fuel Recycling
nesc0576 GEM, Fuel Cycle Cost and Economics for Thermal Reactor, Present Worth Analysis
nesc0711 GEOCOST-BC, Geothermal Power Plant Electricity Generator Cost, Thermodynamics Calculation
iaea1222 HAMCIND, Cell Burnup with Fission Products Poisoning
nea-0176 HETERO, Flux and Power Distribution in Thermal Reactor by 3-D, 2 Group Line Source Sink Method
nea-0100 HYTHEST, Dependence of Fuel Fabrication Tolerances on Hydraulics of BWR, PWR
nea-0353 ICON, Reactor Operation Fission Products Inventory Calculation
nea-1340 INVENT-STUDSVIK, Fission Products Abundances in U235, U238, Pu239 Samples
nea-0434 ISOTEX-1, Time-Dependent Heavy Isotope and Fission Products Concentration in U Reactor or Pu Reactor
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-0417 KOSAK, Power Plant Cost Optimization with Pu Availability Option
nea-0441 KPD, Time-Dependent Fuel Cycle Cost Calculation for Various Reactor Types
nesc0249 LASER, Slowing-Down Neutron Spectra and Burnup for Thermal Reactors, Neutron Transport Theory
nea-0573 LASER-PNC, Neutron Spectra in Uniform Lattice with Burnup Calculation
ccc-0343 LEOPARD-MICRO, Spectrum-Dependent Non-Spatial Fuel Depletion
nea-0965 LOLA-SYSTEM, JEN-UPM PWR Fuel Management System Burnup Code System
nesc9449 LPGC, Levelized Steam Electric Power Generator Cost
ccc-0631 LWRARC, PWR and BWR Spent Fuel Decay Heat Generator
nea-1643 MCB1C, Monte-Carlo Continuous Energy Burnup Code
iaea0889 MCRAC, In Core Fuel Management, Program of PFMP System
nesc9479 MGA, Pu Isotope Abundance from Multichannel Analyzer Gamma Spectra
psr-0455 MONTEBURNS 2.0: An Automated, Multi-Step Monte Carlo Burnup Code System
nesc0798 MSF21/VTE21, Desalination Plant Heat, Mass Balance, Design, Cost Optimization
nea-1845 MURE, MCNP Utility for Reactor Evolution: couples Monte-Carlo transport with fuel burnup calculations
iaea1411 NAAPRO, Neutron Activation Analysis Prognosis and Optimization code
nesc0146 NPRFCCP, Fuel Cycle Cost and Economics for Multi-Region Reactor
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
nesc0699 ORSIM, Nuclear Fuel, Fossil Fuel Hydroelectric Power Plant Cost and Economics
nesc0540 PACTOLUS, Nuclear Power Plant Cost and Economics by Discounted Cash Flow Method
nea-0521 PAS-1, 2-D, 3-D Linear Static and Dynamic Stress Analysis with 2-D Steady-State Temperature Distribution
iaea0819 PELINOMIC, Power Plant Cost Optimization for Dispersed Load Centres
nea-1339 PEPIN, Methodology for Computing Concentrations, Activities, Gamma-Ray Spectra, and Residual Heat from Fission Products.
nesc0454 PHENIX, 2-D MultiGroup Diffusion Fast Reactor Burnup Calculation and Fuel Cycle Analysis
nea-1663 PLUTON, Isotope Generation and Depletion in Highly Irradiated LWR Fuel Rods
nesc0340 POWERCO, Nuclear Power Plant Electricity Cost and Economics
nea-1675 PPICA, Power Plant Investment Cost Analysis
iaea0888 PSU-LEOPARD, Program LEOPARD in PFMP System, Fast Neutron and Thermal Neutron Spectra Calculation
nesc0441 PWCOST, Fuel Cycle Cost and Economics by Present Worth Levelized Method
ccc-0639 RACC-PULSE, Neutron Activation in Fusion Reactor System
ccc-0627 RADAC, Radioactive Decay and Accumulation of Long Lived Isotopes
nea-0475 RASPA, Burnup with Fission Products Inventory, Gamma Spectra, Isotopic Power Density
ccc-0443 REAC*3, Isotope Activation and Transmutation in Fusion Reactors
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
ests0176 RECAP, Replacement Energy Cost for Short-Term Reactor Plant Shut-Down
nesc1065 REFCO83, Nuclear Fuel Cycle Cost Economics Using Discounted Cash Flow Analysis
nea-0262 REFLOS, Fuel Loading and Cost from Burnup and Heavy Atomic Mass Flow Calculation in HWR
nea-1231 REFREP, Near-Field Model for Spent Fuel Repository
nea-0101 REP-3, Time-Dependent Xe and Sm Poisoning from Space-Dependent Flux Distribution
ccc-0137 RIBD, Fission Products Inventory and Delay Heat in Fast Reactors, with Data Library
ccc-0382 RIBD-IRT, Isotope Buildup and Isotope Decay from Fission Source
nea-0239 RIBOT-5, 0-D Burnup for 5 Group BWR or PWR Lattice
nea-0589 RICE-CEGB, Long-Term Actinides and Fission Products Inventory of Irradiated Fuel
nesc0831 RO-75, Reverse Osmosis Plant Design Optimization and Cost Optimization
nea-0598 RSYST, Modular System for Reactor Core and Shielding Problems
nea-1078 SACHET, Dynamic Fission Products Inventory in PWR Multiple Compartment System
nea-1779 SAGEP-FR, Sensitivity Analysis of Fast Reactor Parameters
ccc-0785 SCALE 6.1.2, Modular system for criticality, shielding, source term, fuel depletion/decay, inventories, reactor physics
iaea0913 SCENARIOS, Simulation of Reactor Introduction and Operation Scenario Needs
nea-0235 SCOPERS-2, BWR and PWR Core Performance Simulation
nea-1840 SERPENT 1.1.7, 3-D continuous-energy Monte Carlo reactor physics burnup calculation, lattice physics applications
iaea0925 SHARDA, Thermal Reactor Isotope Irradiation Analysis
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-0842 SRAC-95, Cell Calculation with Burnup, Fuel Management for Thermal Reactors
iaea0882 STAR, Fuel Management of BWR
iaea0900 STOFFEL-1, Steady-State In-Pile Behaviour of Cylindrical H2O Cooled Oxide Fuel Rod
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
nea-1698 SWAT, Step-Wise Burnup Analysis Code System to Combine SRAC-95 Cell Calculation Code and ORIGEN2
iaea0872 TACHY, BWR Fuel Management by 2-D Coarse Mesh Neutron Diffusion
iaea1338 TEMPUL, Temperature Distribution in Fuel Element after Pulse
nea-0486 TOTEM, Demand Assessment for Nuclear Power Plants and Conventional Power Plants
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 2.1.5, 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
nea-1882 XSUN-2013, Windows interface environment for transport and sensitivity-uncertainty software TRANSX-2, PARTISN and SUSD3D
nea-0072 ZADOC, 2 Group Time-Dependent Burnup in X-Y Geometry with Fuel Management
iaea0912 ZZ AMZ, 70-Group 40 Isotope Multigroup Library for Fast Reactor Calculation
dlc-0089 ZZ LUMP, Lumped Fission Product Cross-Section Library for Fast Reactor Analysis from ENDF/B-V
dlc-0038 ZZ ORYX-E/38B, Group Constant Library from ENDF/B Fission Product Data for ORIGEN Calculation