| nesc0374 | 1-DX, 1-D Diffusion for Fast Reactor MultiGroup Cross-Sections, Group Constant Collapsing | |
| nesc0325 | 2-DB, 2-D MultiGroup Diffusion, X-Y, R-Theta, Hexagonal Geometry Fast Reactor, Criticality Search | |
| nea-1250 | 2D-SEEP, 2-D Ground Water Flow in Permeable Geologic Media | |
| nesc0806 | 2DEPEP, Partial Differencial Equation Solution and Eigenvalues for Potential and Diffusion Problems | |
| nesc9739 | 2DFLOW, 2-D Drainage Winds and Diffusion Simulation | |
| iaea1386 | 2GWIHLIB, Generation and Plot of Cross Sections for HYDMN | |
| nesc0567 | 3-DB, 3-D MultiGroup Diffusion, X-Y-Z, R-Theta-Z, Triangular-Z Geometry, Fast Reactor Burnup | |
| nea-1732 | 3D-TRANS-2003, Workshop on Common Tools and Interfaces for Radiation Transport Codes | |
| nesc9588 | 3DGEOELE, 3-D Nonlinear Least Square Fit | |
| psr-0248 | ABAREX, Optical Statistical Model Neutron Cross-Sections Using ABACUS and NEARREX | |
| nea-0912 | ABLEIT-TRANS, Isotope Concentration and Sensitivities on Cross-Sections Data | |
| nea-0976 | ACCULIB, Program Library of Mathematical Routines | |
| ccc-0442 | ACDOS3, Neutron Activation Activities and Dose Rates | |
| nea-1072 | ACFA, Isotope Activation of Coolant and Structure Materials | |
| csni1015 | ACHILLES, Heat Transfer in PWR Core During LOCA Reflood Phase | |
| iaea0975 | ACORNS, Covariance and Correlation Matrix Diagonalization | |
| nea-0621 | ACRO, Organ Doses from Acute or Chronic Radioactive Inhalation or Ingestion | |
| ccc-0372 | ACT-ARA, Time-Dependent Radiation Source Terms | |
| nea-0511 | ACTIV, Sandwich Detector Activity from In-Pile Slowing-Down Spectra Experiment | |
| iaea0960 | ACTIV-JINR, Experimental Gamma Spectra Unfolding | |
| iaea1380 | ACTIVATE2007, Activation Cross Section by Combining Cross Section and Multiplier (ENDF Fomat) | |
| ests0171 | ADASAGE, ADA Application Development System | |
| nea-0480 | ADDELT, Scattering Law Correlation for Delta Function Phonon Spectra | |
| nea-1708 | ADEFTA 4.1, Atomic Densities for Transport Analysis | |
| psr-0190 | ADENA, Fission Products Beta Spectra and Gamma Spectra in 19 Group from U235 Pu239 Mixture | |
| nesc0465 | ADLER, ENDF/B Adler-Adler Resonance Parameter to Point Cross-Sections with Doppler Broadening | |
| nesc0908 | AERIN, Organ and Tissue Doses from Radioactive Aerosols | |
| ests0165 | AES, Automated Construction Cost Estimation System | |
| ccc-0360 | AIRDIF, Neutron and Gamma Doses from Nuclear Explosion by 2-D Air Diffusion | |
| nea-0001 | AIREK-MOD, Time Dependent Reactor Kinetics with Feedback Differencial Equation | |
| nea-0002 | AIREK-PUL, Periodic Kinetics Problems of Pulsed Reactors | |
| iaea1274 | AIREKMOD-RR, Reactivity Transients in Nuclear Research Reactors | |
| nea-1130 | AIRGAMMA, External Gamma-Ray Exposure from Radioactive Cloud | |
| nesc0326 | AIROS-2A, Space-Independent Reactor Kinetics and Space-Dependent Heat Transfer, Mass Transfer | |
| ccc-0341 | AIRSCAT, Dose Rate from Gamma Air Scattering by Single Scattering Approximation | |
| ccc-0110 | AIRTRANS, Time-Dependent, Energy Dependent 3-D Neutron Transport, Gamma Transport in Air by Monte-Carlo | |
| nea-0590 | AKIMA'S-SPLINE, Curve and Surface Fit of Uni-Variate and Bi-Variate Function | |
| nea-0500 | ALARM, Thermohydraulics of BWR with Jet Pumps During LOCA | |
| nea-0705 | ALARM-P1, PWR Thermohydraulics for ECCS During Blowdown | |
| nea-1353 | ALBEDO ALBEZ, Gamma and Neutron Attenuation in Air Ducts | |
| nea-0108 | ALCI, Homogenious 2-D MultiGroup Neutron Diffusion in X-Z, R-Z, R-Theta Geometry with Criticality Search | |
| ccc-0577 | ALDOSE, Dose Rate from Alpha Disk Source in H20 | |
| psr-0146 | ALICE91, Particle Spectra from Compound Nucleus Decay | |
| ccc-0558 | ALKASYS, Rankine-Cycle Space Nuclear Power System | |
| nesc9658 | ALPHA/AMPU, Radionuclide Radioactivity from Alpha Spectrometer Measurements | |
| ccc-0612 | ALPHN, (Alpha, N) Neutron Production in High-Level Waste Canisters | |
| nea-0585 | ALPS, Solid-State Detector Alpha Spectra Unfolding | |
| nesc0815 | ALVIN, Diffusion and Integral Data Comparison and Sensitivity Analysis | |
| nea-0675 | AMALTHEE, Emission Spectra for N, D, H3, He3, He4 Induced Reactions | |
| nea-0403 | AMARA, Correlation of Nuclear Data to Integral Experiment by Lagrange Multipliers | |
| nesc0562 | AMDLIBAE, IBM 360 Subroutine Library, Special Function, Polynomials, Differencial Equation | |
| nesc0563 | AMDLIBF, IBM 360 Subroutine Library, Eigenvalues, Eigenvectors, Matrix Inversion | |
| nesc0564 | AMDLIBGZ, IBM 360 Subroutine Library for Data Processing, Graphics, Sorting | |
| iaea1251 | AMICO, Cross-Sections Data for ANISN, DOT from WIMS Library | |
| psr-0315 | AMPX-77, Modular System for Coupled Neutron-Gamma MultiGroup Cross-Sections from ENDF/B-5 | |
| uscd0795 | AMRAW, Risk Assessment Method for Radioactive Waste Management | |
| nesc0486 | ANCON, Space-Independent Reactor Kinetics with Linear or Nonlinear Thermal Feedback | |
| nea-1235 | AND, Atomic Number Densities for Criticality Calculation | |
| nea-0321 | ANDROMEDA, 1-D Burnup for Fuel Cycle Analysis of FBR | |
| nea-1798 | ANGELO-LAMBDA, Covariance matrix interpolation and mathematical verification | |
| nea-0633 | ANIPLO-50, Plot of Scalar Flux and Dose Rates from ANISN Calculation | |
| ccc-0254 | ANISN, 1-D Neutron Transport and Gamma Transport in Slab, Cylindrical, Spherical Geometry with Anisotropic Scattering | |
| ccc-0082 | ANISN-E, 1-D Transport Program ANISN with Exponential Model | |
| nea-0363 | ANISN-FONTENAY, 1-D Planar, Spherical, Cylindrical Neutron Transport and Gamma Transport with Deep Penetration | |
| ccc-0255 | ANISN-W, 1-D Transport Calculation for Deep Penetration Problems | |
| ccc-0514 | ANISN/PC, MultiGroup 1-D Discrete Ordinates Transport with Anisotropic Scattering | |
| nea-1638 | ANITA-2000, Isotope Inventories from Neutron Irradiation, for Fusion Applications | |
| nea-1343 | ANITA-4, Isotope Inventories from Neutron Irradiation, for Fusion Applications | |
| nea-1657 | ANL-BPB, Argonne National Laboratory Code Center Benchmark Problem Book | |
| nea-0470 | ANSCLAD-1, Creep Strain in Fuel Pin Zircaloy Clad During Temperature Transient | |
| nesc0529 | ANVENT, Temperature Distribution and Pressure in Containment and Ice Condenser after LOCA for LWR | |
| nesc9977 | ANYOLS, Least Square Fit by Stepwise Regression | |
| nesc0858 | APACHE, 2-D Chemical Reactive Fluid Flow Dynamic for CW Chemical Lasers | |
| nea-0546 | APPLE, Plot of 1-D MultiGroup Neutron Flux and Gamma Flux and Reaction Rates from ANISN | |
| nea-0367 | APPROX, 1-D and 2-D Function Approximation by Polynomials, Splines, Finite Elements Method | |
| nea-0445 | APS-2, Elastic Behaviour of Piping System | |
| psr-0065 | APSAI, Activation Calculation and Plot of Neutron Spectra, Gamma Spectra by ANISN | |
| iaea1219 | APUD-3.0, Off-Site Contamination Assessment from Accidental Release | |
| ests1169 | ARCON96, Radioactive Plume Concentration in Reactor Control Rooms | |
| nea-0320 | ARGO, 1-D Neutron Diffusion in Slab, Cylindrical, Spherical Geometry from JAERI Fast-Set, ABBN, RCBN | |
| nesc0152 | ARGUS, Transient Temperature Distribution Cylindrical Geometry, Space-Dependent or Time-Dependent Heat Generator | |
| nea-1368 | ARIANNA-2, Sub-Compartment Thermo-Hydraulic Transients in LOCA | |
| nea-0174 | ARLEKIN, General Point Reactor Kinetics by Lie-Series Method | |
| nesc0925 | ARRRG/FOOD, Doses from Radioactive Release to Food Chain | |
| nesc0738 | ARSTEC, Nonlinear Optimization Program Using Random Search Method | |
| nea-1581 | ART MOD2, Fission Product Migration in Primary System and Containment | |
| nea-0539 | ASCOT-1, Thermohydraulics of Axisymmetric PWR Core with Homogeneous Flow During LOCA | |
| nea-1006 | ASDIC, Fast Reactor Hexagonal 3 Component Fuel Pin Diffusion Coefficient | |
| nea-0661 | ASNBILD, Generator of JCL and Data for Program ANISN on CDC Computer | |
| ccc-0126 | ASOP, Shield Calculation, 1-D, Discrete Ordinates Transport | |
| ests0803 | ASR4, 4-Gage Anelastic Strain Recovery Analysis | |
| nesc0580 | ASTEM, Evaluation of Gibbs, Helmholtz and Saturation Line Function for Thermodynamics Calculation | |
| ccc-0417 | AT123D, 1-D, 2-D, 3-D Transient Waste Transport Simulation in Groundwater | |
| nesc0417 | ATHENA-4, Inelastic Scattering Form Factors for Woods-Saxon or Harmonic Potential | |
| psr-0431 | ATHENA_2D, Simulation Hypothetical Recriticality Accident in a Thermal Neutron Spectrum | |
| ccc-0179 | ATR, Radiation Transport Models in Atmosphere at Various Altitudes | |
| iaea0906 | AUJP, Optical Potential Parameter Search by CHI**2 Method | |
| ccc-0519 | AUS, Neutron Transport and Gamma Transport System for Fission Reactors and Fusion Reactors | |
| psr-0008 | AUTOJOM, Quadratic Equation Coefficient for Conic Volume, Parallelepipeds, Wedges, Pyramids | |
| nea-1076 | AVACOM-ETAP, Availability and Element Transient and Asymptotic Repair Process | |
| nesc9700 | AVPROG, Monte-Carlo Simulation of System Availability | |
| nea-0861 | AWE-1 AWE-2 BRUNA, Minimal Cut Sets of Logic Trees | |
| nesc0191 | AX-TNT, Super Prompt Critical Excursions in Spherical Geometry, Thermohydraulics | |
| nea-0179 | AXIFLUX, Cosine Function Fit of Experimental Axial Flux in Cylindrical Reactor | |
| psr-0075 | AXMIX, ANISN Cross-Sections Mixing, Transport Corrections, Data Library Management | |
| psr-0297 | AXMIX-PC, Cross-Sections Generator for ANISN, DOT from Different Sources | |
| nesc9564 | AYER, 2-D Thermal Conduction by Finite Element Method | |
| nesc1020 | BACFIRE, Minimal Cut Sets Common Cause Failure Fault Tree Analysis | |
| uscd1158 | BALANCE, Mass Transfer in Groundwater Aqueous Solution | |
| nesc9677 | BARMOM, Fission Barriers and Moments of Inertia | |
| iaea0953 | BASACF, Integral Neutron Spectra Adjustment and Dosimetry | |
| nea-0636 | BASKER, Isotropic Scattering Kernel Calculation Using VIWI | |
| uscd1040 | BAYESZ, S-Wave, P-Wave Resonance Level Spacing and Strength Functions | |
| nesc0767 | BEACON/MOD3, 1-D and 2-D 2 Phase Flow and Heat Transfer in Containment, LWR LOCA | |
| iaea0827 | BEAT, Reactor Response and Reactivity Analysis | |
| nea-0949 | BERMUDA, 1-D, 2-D, 3-D Neutron and Gamma Transport for Shielding | |
| 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-0117 | BETA-2B, Time-Dependent Bremsstrahlung Transport, Electron Transport by Monte-Carlo Method | |
| ccc-0657 | BETA-S, Multi-Group Beta-Ray Spectra | |
| csni0076 | BETHSY/6.9C, Loss of residual heat removal system during mid-loop operation | |
| csni0062 | BETHSY/9.1B, Cold Leg Break Test | |
| nea-0591 | BEVE, Isotope Buildup in LWR Fuel Pin with Self-Shielding in Pellet | |
| nea-0541 | BICUSP, Solution and Derivatives of 2-D Function in Rectangular Mesh Grid by Splines | |
| nea-0188 | BIGGI-4T, Gamma Transport in Multi-Region Shield in Planar or Spherical Geometry | |
| ests0298 | BIMOND3, Monotone Bivariate Interpolation | |
| nesc1037 | BIMOND3, Monotone Bivariate Interpolation | |
| psr-0117 | BINX, MINX Utility and SPHINX Utility, BCD to BIN Library Conversion | |
| nea-0870 | BISON, 1-D Burnup and Transport in Slab, Cylindrical, Spherical Geometry | |
| iaea0820 | BLAST, Accident Conditions in Critical and Subcritical Thermal Reactor System | |
| psr-0377 | BLOCKAGE2.5R, Plug of Emergency Core Cooling Suction Strainers by Debris BWR | |
| nea-0683 | BLOK, Turbulent Flow in Pipes and Channels with Rectangular Obstruction | |
| nea-0978 | BLOOM, Principal Component Analysis and Correspondence Analysis Using IMSL Subroutines | |
| ccc-0633 | BLT, Waste Transport through Porous Media from Container Failure | |
| nea-0660 | BOB-7, Ge(Li) Detector Gamma Spectra Unfolding | |
| 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 | |
| iaea1246 | BOMJ, Level Assignments from Gamma Spectra Measurements | |
| psr-0173 | BON, Unfolding of Multisphere Spectrometer Neutron Spectra | |
| nea-1187 | BOREAS, Nuclear and Thermohydraulic LWR Burnup Simulation | |
| nea-1678 | BOT3P5.2, 3D Mesh Generator and Graphical Display of Geometry for Radiation Transport Codes, Display of Results | |
| nea-1523 | BOXER, Fine-flux cross section condensation, 2D few group diffusion and transport burnup calculations | |
| iaea0915 | BRA, Breast Radiation Analysis from Mammography | |
| nea-0516 | BRANCALEONE, Transfer Function Roots for Linear System of Several Variables | |
| psr-0143 | BREESE, Distribution Function for Program MORSE from Albedo Data | |
| iaea1190 | BRETISLAV,OLDRICH, Neutron Diffusion in Hexagonal Geometry for WWER Critical Fuel Assemblies | |
| nesc9804 | BRGLM, Interactive Linear Regression Analysis by Least Square Fit | |
| nea-0390 | BRIGITTE, Dose Rate and Heat Source and Energy Flux for Self-Absorbing Rods | |
| nea-0438 | BRIGITTE-KA, ENDF/B to KEDAK Data Conversion with Resonance Cross-Sections Tables Generator | |
| nea-0418 | BRUCH-D-06, LOCA of PWR Primary System with 23 Control Volume and 9 Rupture Points | |
| nea-0866 | BTPLOT BTSPEC EXSPEC ORDTAB TABLST, Retrieval of ENDF/B Decay Spectra | |
| nesc0667 | BUCKLE, Time-Dependent Deformation of 1-D Oval Pipe Under Pressure, Temperature, Neutron Flux | |
| nea-1727 | BULK-I, Radiation Shielding Tool for Proton Accelerator Facilities | |
| nea-1771 | BULK_C-12, N & photon effective dose rates from medium energy protons or carbon ions through concrete or concrete/iron | |
| nea-1819 | BURD, Bayesian estimation in data analysis of Probabilistic Safety Assessment | |
| 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-0114 | BURST, Time-Dependent Pression and Coolant Flow after Circuit Fracture in HTGR | |
| nesc0435 | BURST-1, Rupture of 1-D Cylindrical Pressurized Liquid System, Hydrodynamic Calculation | |
| nea-0558 | BUST, Elastic Stress in HTGR Pressurized Fuel Elements | |
| nea-0159 | BWCAL, Void Distribution and Flow Velocity in BWR | |
| uscd1151 | BWIP-RANDOM-SAMPLING, Random Sample Generation for Nuclear Waste Disposal | |
| nesc1080 | BWR-GALE, Radioactive Gaseous and Liquid Waste Release from BWR | |
| ccc-0485 | BWR-LTAS, BWR Long Term Accident Simulation Program | |
| nea-1313 | BWRDYN, Thermal Hydraulic Analysis of a BWR Plant | |
| nea-1044 | BWRPLANT/ZERO, Dynamic Model for BWR Nuclear Plant | |
| iaea1403 | C-SHIELDER, Gamma shielding calculations of radionuclides emitting photons 0.5 to 10 MeV by different concretes | |
| ccc-0476 | CAAC, System to Implement Atmospheric Dispersion Assessments | |
| csni2100 | CABRI-REPNa-1 TEST, Assessment of fuel behaviour mechanisms relevant for RIA transients | |
| csni2106 | CABRI-REPNa-10 TEST, Assessment of fuel behaviour mechanisms relevant for RIA transients | |
| csni2101 | CABRI-REPNa-2 TEST, Assessment of fuel behaviour mechanisms relevant for RIA transients | |
| csni2102 | CABRI-REPNa-3 TEST, Assessment of fuel behaviour mechanisms relevant for RIA transients | |
| csni2103 | CABRI-REPNa-4 TEST, Assessment of fuel behaviour mechanisms relevant for RIA transients | |
| csni2104 | CABRI-REPNa-5 TEST, Assessment of fuel behaviour mechanisms relevant for RIA transients | |
| csni2105 | CABRI-REPNa-8 TEST, Assessment of fuel behaviour mechanisms relevant for RIA transients | |
| nea-1020 | CADE, Multiple Particle Emission Cross-Sections by Weisskopf-Ewing Theory | |
| nesc0270 | CAESAR-4, 1-D MultiGroup Diffusion in Slab, Cylindrical, Slab Geometry, Criticality Search | |
| nea-1800 | CAFDATS, Converter of Angular Fluxes of DORT, ANISN and TORT Systems | |
| nea-1278 | CALENDF-2005, Pointwise, Multigroup Neutron Cross-Sections and Probability Tables from ENDF/B Evaluations | |
| ccc-0610 | CALOR95, High-Energy Calorimeter Design and Data Evaluation by Monte-Carlo | |
| ccc-0240 | CAMERA CAM, Radiation Dose Absorption by Computer Man | |
| ccc-0542 | CAP-88, Dose Risk Assessment from Air Emissions of Radionuclides | |
| nea-1327 | CAPCAL, 3-D Capacitance Calculator for VLSI Purposes | |
| nea-0290 | CARBOX, Equilibrium of Non-Stoichiometric Mixtures of Oxides, Carbides, Methane | |
| nesc0638 | CAREN-4, ENDF/B Utility, Discontinuity Check at Resonance Region Boundary | |
| psr-0388 | CARES, Seismic Structure Safety Analysis for Nuclear Power Plants | |
| ests0012 | CARES-ESTSC, Seismic Structure Safety Analysis for Nuclear Power Plants | |
| nea-1735 | CARL 2.3, radiotoxicity, activity, dose and decay power calculations for spent fuel | |
| nea-0649 | CARMEN-SYSTEM, Programs System for Thermal Neutron Diffusion and Burnup with Feedback | |
| nea-0393 | CARNAC, Neutron Flux and Neutron Spectra in Criticality Accident | |
| psr-0131 | CARP, Flux Conversion from Program DOT to Currents for Program BREESE | |
| ccc-0024 | CARSTEP, Particle Flux on Space Vehicle in Van Allen Zone | |
| nesc0482 | CASCADE, Intranuclear Gamma Cascade Calculation for Particle Emission Probability | |
| nesc0742 | CASIM, High Energy Cascades in Shields of Arbitrary Geometry Using Monte-Carlo Method | |
| psr-0262 | CASKCODES, Program CAPSIZE Scope KWIKDOSE for Shipping Cask Shielding | |
| nea-1195 | CASKET, Thermal and Structural Analyses for Transport and Storage Cask | |
| nea-0712 | CASSANDRE, 2-D Reactor Dynamic FEM Program with Thermohydraulic Feedback | |
| nea-1395 | CASTHY, Statistical Model for Neutron Cross-Sections and Gamma-Ray Spectra | |
| nesc0892 | CCC, Heat Flow and Mass Flow in Liquid Saturated Porous Media | |
| iaea1347 | CCRMN, N, P, He4, D, H3, He3 Reaction Calculation for Medium-Heavy Targets | |
| nesc9789 | CDMS, Cost Data Management System Spread Sheet | |
| iaea0920 | CEBIS, 1-D 2 Group Diffusion Code for Reactor Calculation | |
| nesc0548 | CEBUG, 3-D Transient Hydraulics for Na H2O Reaction by Finite Elements Method | |
| ests1071 | CECP, Decommissioning Costs for PWR and BWR | |
| nea-0553 | CEDRAZAL, Steady-State Heat Transfer in HTR with Multifuel Region | |
| psr-0532 | CEM03.01, Monte-Carlo Code system to calculate nuclear reactions in the framework of the improved cascade-exciton model | |
| iaea1247 | CEM95, Cascade Exciton Model Nuclear Reactions by Monte-Carlo Method | |
| ccc-0544 | CEPXS ONELD, 1-D Coupled Electron Photon MultiGroup System | |
| nea-0648 | CERBERO, Cross-Sections by Optical, Statistical Model for Spin 0, Spin 1/2 Particles | |
| nesc0415 | CEXE INCEXE, 1 Group 3-D Time-Dependent Xe Oscillations in X-Y-Z Geometry with Feedback | |
| ests0663 | CFDLIB05, Computational Fluid Dynamics Library | |
| nesc9537 | CFEST-1.1, Coupled Fluid, Energy, Solute Transport in Ground-Water System | |
| iaea1266 | CFUP1, Neutron or Charged-Particle Reactions of Fissile Nuclei up to 33 MeV | |
| iaea1405 | CHAINFINDER 2.16, search for transmutation chains under neutron irradiation | |
| ccc-0604 | CHAINS-PC, Decay Chain Atomic Densities | |
| iaea1404 | CHAINSOLVER 2.20, transmutation simulation of samples during irradiation in nuclear reactors | |
| ccc-0584 | CHAINT-MC, 2-D Radionuclide Transport in Fractured Porous Medium | |
| ccc-0070 | CHARGE-2/C, Flux and Dose Behind Shield from Electron, Proton, Heavy Particle Irradiation | |
| uscd1208 | CHECKR, ENDF/B Format Check | |
| nea-1561 | CHEMENGL/CHIMISTE, Chemical and Physical Properties of Elements | |
| nea-1346 | CHEMTARD, Simulation of Chemical Species Through Porous Media | |
| nesc9774 | CHEMTRN, Chemical Species Transport in Groundwater System | |
| nesc0611 | CHILES, Singularity Strength of Linear Elastic Bodies by Finite Elements Method | |
| ests0802 | CHMTRNS, Non-Equilibrium Chemical Transport Code | |
| nea-0716 | CHOLESK, Diffusion Calculation with 2-D Source in X-Y or R-Z Geometry | |
| uscd1021 | CHUCK-3, Nuclear Scattering Amplitude and Collision Cross-Sections by Coupled Channel | |
| nea-0451 | CICLON, Neutronics Calculation for PWR Transition Fuel Cycle Management | |
| nesc0313 | CINDER, Depletion and Decay Chain Calculation for Fission Products in Thermal Reactors | |
| nesc9602 | CIRCLE-SPLINE, 2-D, 3-D Spline Curve Fitting | |
| 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 | |
| iaea1385 | CITOPP,CITMOD,CITWI, Processing codes for CITATION Code | |
| nea-0631 | CLAPTRAP, Pressure Transients in LWR Containment During LOCA | |
| nesc0540 | CLOTHO, Mass Flow Data Calculation for Program PACTOLUS | |
| iaea0883 | CLUB, Cell Calculation PF Candu PWR Fuel Clusters | |
| nea-0864 | CLUHET, Steady-State Thermohydraulics of Rod Bundles with 1 Phase Flow | |
| nea-0357 | CLUP-77C, Collision Probability and Neutron Flux Distribution in Multi-Region Fuel Cluster | |
| nea-0255 | CLUS, Heat Transfer and Fuel Power in Liquid Cooled 7 Rod Fuel Elements Cluster | |
| nesc0188 | CMPXMAT, Transfer Function Calculation for Linearized Differential Equation | |
| iaea1265 | CMUP2, Reaction Cross-Sections for N, P, D, T, He3, He4 up to 50 MeV | |
| nesc0873 | COAST-4, Design and Cost of Tokamak Fusion Reactors | |
| nesc0432 | COBRA, Transient Thermohydraulics Fuel Elements Clusters, Subchannel Analysis Method | |
| nesc9978 | COBRA-3C/RERTR, Thermohydraulic Low Pressure Subchannel Transients Analysis | |
| nea-1614 | COBRA-EN, Thermal-Hydraulic Transient Analysis of Reactor Cores | |
| ests0135 | COBRA-SFS CYCLE3, Thermal Hydraulic Analysis of Spent Fuel Casks | |
| nesc1091 | COBRA-SFS, Thermal Hydraulics of Spent Fuel Storage System | |
| nea-0294 | CODAC, MultiGroup Cross-Sections Generation from ENDF/B for Monte-Carlo Program TIMOC | |
| ccc-0724 | COG10, Multiparticle Monte Carlo Code System for Shielding and Criticality Use | |
| nea-0915 | COGEND, Decay Data Generated in ENDF-6 Format | |
| nesc9994 | COIFES, Structure Graphics for Finite Elements Method Using Hidden Line Technique | |
| nea-1126 | COLLI-PTB, Neutron Fluence Spectra for 3-D Collimator System by Monte-Carlo | |
| nea-0903 | COLUMN, 1-D Migration for Various Physical Chemical Processes | |
| psr-0286 | COMBINE-PC, MultiGroup Neutron Cross-Sections in B1 or B3 Approximation from ENDF/B-5 | |
| nesc0704 | COMCAN, Fault Tree Analysis, Minimal Cut Sets for Common Cause Failure | |
| nea-0340 | COMET, Mechanical and Thermal Stress in Fuel Element Clad | |
| psr-0343 | COMIDA, Radionuclide Food Chain Model for Acute Fallout Deposition | |
| psr-0302 | COMNUC3B, Gamma Emission, Neutron Emission Fission and Scattering Cross-Sections Using Hauser-Feshbach | |
| iaea0966 | COMPAR, NJOY, GROUPIE, FLANGE-2, ETOG-3, XLACS MultiGroup Cross-Sections General Comparison | |
| nesc0702 | COMPARE, Transient Subcompartment Thermodynamics Analysis with 2 Phase Vent Flow | |
| nesc0776 | COMPARE-MOD1 COMPARE-MOD1A, 2 Phase Flow Thermodynamics, Pressure in LWR Containment | |
| ests0023 | COMPBRN3, Modelling of Nuclear Power Plant Compartment Fires | |
| iaea1321 | COMPLOT2007, Compare ENDF/B Plots of Reaction Data | |
| nesc0649 | COMQC, Quality Control Statistical Analysis for Means, Errors, Skewness, Kurtosis | |
| nea-1578 | COMRAD96, Nuclear Fuel Burnup and Depletion Calculation System | |
| nesc0663 | COMRADEX-4, Doses from Radioactive Release, Meteorological Dispersion, Aerosol | |
| iaea0928 | COMTA, Ceramic Fuel Elements Stress Analysis | |
| uscd1203 | COMTRANS, ENSDF Comment Font Case Translator | |
| nesc0498 | CONCEPT-5, Cost and Economics Analysis for Nuclear Fuel or Fossil Fuel Power Plant | |
| ests0680 | CONCHAS-SPRAY, Reactive Flows with Fuel Sprays | |
| nea-0325 | CONDENSE, Conversion of JAERI Fast-Set to ABBN Format with Self-Shielding | |
| nea-0946 | CONDN-63B, Thermohydraulics of Nuclear Power Plant Condenser | |
| nea-0427 | CONDOR-3, Local and Spectrum Dependent Burnup with Mesh-Wise Depletion | |
| ccc-0416 | CONDOS-II, Radiation Dose from Consumer Product Distribution Chain | |
| nesc0433 | CONTEMPT, LWR Containment Pressure and Temperature Distribution in LOCA | |
| nesc0818 | CONTEMPT-4MOD3, LWR Containment Long-Term Pressure Distribution and Temperature Distribution in LOCA | |
| iaea1307 | CONVERT2007, FORTRAN Program Converter for Different Computers | |
| psr-0017 | COOLC, Ne-213 Liquid Scintillation Detector Neutron Spectra Unfolding | |
| nea-1305 | COOLOD, Steady-State Thermal Hydraulics of Research Reactors | |
| csni1023 | CORA-13 experiment on severe fuel damage, core degradation and quench | |
| csni1024 | CORA-W2 Experiment on Severe Fuel Damage for a VVER-type PWR | |
| nea-0567 | CORAN, PWR and BWR Containment Response to LOCA | |
| iaea1226 | CORD, PWR Core Design and Fuel Management | |
| nesc0758 | COREL, Ion Implantation in Solids, Range, Straggling Using Thomas-Fermi Cross-Sections | |
| nesc0759 | CORTES, Steady-State and Transient Heat Flow and Stress Analysis in Pipe Joints | |
| nea-0383 | COSANI-2, Gamma Doses from SABINE Calculation, Activity from ANISN Flux Calculation | |
| nea-1375 | COSIMA, BWR Core Performance Simulator | |
| nea-0067 | COSTANZA, 1-D 2 Group Space-Dependent Reactor Dynamics of Spatial Reactor with 1 Group Delayed Neutrons | |
| nea-0160 | COSTANZA-AX, 1-D Neutronics and Thermodynamics of Liquid Cooled Reactor in Axial Geometry | |
| nea-0333 | COSTANZA-RZ, 1-D Liquid Cooled Reactor Dynamic in R-Z Geometry | |
| nea-0425 | COSTANZA-XE, 2-D Pebble-Bed or Prismatic Fuel Elements HTR Dynamic in Cylindrical Geometry | |
| nea-0398 | COSTAX-BOIL, Transient Dynamic Analysis of BWR and PWR in Axial Geometry | |
| nea-0533 | COSTAX-BWR, Coupled Time-Dependent 2 Group Neutron Diffusion and 2 Phase Fuel Rod Coolant Flow | |
| nea-0574 | COVAL, Compound Probability Distribution for Function of Probability Distribution | |
| nesc9577 | CPDES2, Coupled 2-D Partial Differencial Equation Solution | |
| nesc9576 | CPDS3, Coupled 3-D Partial Differencial Equation Solution | |
| ccc-0419 | CRAC2, Reactor Accident Risk Assessment | |
| nea-0463 | CRACKLE, Fast Reactor Pu Fuel Management | |
| nea-0057 | CRAM-360, 1-D, 2-D Multi Group Diffusion with Keff Calculation or Criticality Search | |
| nea-0718 | CRAPONE, Optical Model Potential Fit of Neutron Scattering Data | |
| nea-0948 | CRECT-J, Input Preparation of Evaluated Data in ENDF-4, ENDF-5 and ENDF-6 Formats | |
| nesc9958 | CREEP-80, Creep Analysis of Concrete Structure by Finite Element Method | |
| nesc9678 | CRI, 4-Processor VAX-11/780 Simulation of CRAY Multitasking System | |
| nea-1734 | CRISSUE-S, Neutronics/Thermal-hydraulics Coupling in LWR Technology | |
| iaea0873 | CRITIC, In-Core Fuel Management for CANDU PWR | |
| nea-1681 | CRITICALITYACCIDENTS, A Review of Criticality Accidents, 2000 Revision, LA-13638 in PDF format | |
| nesc9829 | CROSSPLOT-3/CON-3D, 3-D and Stereoscopic Computer-Aided Design Graphics | |
| ccc-0518 | CRRIS, Health Risk Assessment from Atmospheric Releases of Radionuclides | |
| nea-1040 | CRUNCH, Dispersion Model for Continuous Dense Vapour Release in Atmosphere | |
| ccc-0233 | CRYSTAL-BALL, Neutron Spectra Calculation from Activation Experiment with Error Estimate | |
| nesc9636 | CUBESIM, Hypercube and Denelcor Hep Parallel Computer Simulation | |
| nea-0507 | CURFIT SURFIT, 2-D Polynomial Least Square Fit to Experimental Data | |
| nesc9533 | CURVE LSFIT, Gamma Spectrometer Calibration by Interactive Fitting Method | |
| nea-0247 | CYGAS, 3-D Gamma Flux in Axial or Cylindrical Shields from Cylindrical Source | |
| nea-0494 | CYLDOS, Dose Rate in Cylindrical Shield from Cylindrical Source | |
| nea-0371 | CYLFUX, Fast Reactor Reactivity Transients Simulation in LWR by 2-D 2 Group Diffusion | |
| nea-1416 | D3D/D3E, 2-D, 3-D MultiGroup Neutron Diffusion in Rectangular, Cylindrical, Triangular-Z Geometry | |
| ccc-0273 | DACRIN, Dose in Respiratory Tract and Organs from Aerosol Inhalation | |
| nea-0151 | DANCOFF-3, Dancoff Correction for Cylindrical Fuel Rod at H2O Gaps and for Fuel Clusters | |
| nea-1516 | DANCOFF-MC, Dancoff Correlation for Arbitrary Lattices by Monte-Carlo | |
| nea-0103 | DANG, Elastic and Direct Inelastic and Reaction Neutron Cross-Sections, Deformed Even-Even Nuclei | |
| nea-0694 | DANTE, Activation Analysis Neutron Spectra Unfolding by Covariance Matrix Method | |
| ccc-0366 | DASH, Void Tracing Sn and Monte-Carlo Coupling Program with Angular Fluxes from DOT Program | |
| ests0357 | DASH-FP, Multicomponent Time-Dependent Concentration Diffusion | |
| nea-0646 | DASQHE, Dancoff Correlation for Infinite Circular Rod Assembly in Square or Hexagonal Lattice | |
| nesc9918 | DASSL, Solution of Differencial Algebraic Equation | |
| nesc9493 | DATING, Temperature for Spent Fuel Dry Storage | |
| 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 | |
| ccc-0520 | DCTDOS, Neutron and Gamma Penetration in Composite Duct System | |
| nea-0229 | DCXE, Time-Dependent Xe Diffusion in Non-Multiplying Slab | |
| ests0848 | DDASAC, Double-Precision Differential or Algebraic Sensitivity Analysis | |
| iaea1290 | DDCS, P, D, T, He3, He4 Reactions with 5 Particle Emission by Optical Model | |
| nesc0640 | DE/STE/INTRP, 1st Order Ordinary Differencial Equation for Initial Value Problems | |
| nea-0834 | DEEBAR, Resonance Level Spacing Calculation by Dyson-Metha Optimum Statistics | |
| ccc-0455 | DEIS, Impact Measures of Low Level Radioactive Waste Disposal | |
| ccc-0257 | DELFIC-TES, Gamma Doses from Nuclear Explosion Radioactive Clouds | |
| nea-0446 | DELIGHT-7, Point Reactivity Burnup for HTGR Lattice with P1 Neutron Scattering Approximation | |
| nesc9681 | DEM4-26, Least Square Fit for IBM PC by Deming Method | |
| nesc0754 | DEMONR, Monte-Carlo Shielding Calculation for Neutron Flux and Neutron Spectra, Teaching Program | |
| ests0763 | DENDRO, Cluster Analysis of Experimental Data with Tree Plot | |
| nea-0840 | DENZ, Dense Toxic or Explosive Gases Dispersion in Atmosphere | |
| nea-0453 | DEPCO-MULTI, Subcooled Decompression in PWR Primary System LOCA | |
| psr-0523 | DEPLETOR Version 2, provides depletion capability to the Purdue Advanced Reactor Core Simulator (PARCS) code | |
| iaea0891 | DIAG, 2-D Plotting Program for PDP-11/34 | |
| nea-0672 | DIAMANT-2, MultiGroup Neutron Transport with Anisotropic Scattering in Triangular Geometry | |
| iaea1308 | DICTIN2007, Reaction Index Generated for ENDF Format | |
| ccc-0649 | DIF3D 8.0/VARIANT8.0, 2-D 3-D Multigroup Diffusion/Transport Theory Nodal & Finite Difference Solver, Variational Method | |
| iaea1269 | DIFBAS, Spectra Unfolding of Ne213 P Recoil Detectors | |
| nea-0667 | DIFFAX, Axial Streaming for Hexagonal Lattices in Gas Cooled FBR, Slab Geometry Diffusion | |
| nesc0737 | DIFFUSER, 2-D and 3-D Diffuser Performance, Boundary Layer and Turbulent Flow | |
| nea-0808 | DIFFUSION-ACE, 3-D Neutron Diffusion by Leakage Iteration Method | |
| nea-1067 | DIFMOD, Radionuclide Leaching and Cement Corrosion in Brine | |
| iaea0952 | DIGA/NSL, 3 Regions Lattice Cell Neutron Flux Diffusion Calculation | |
| nesc9639 | DIGLIB, General Graphics Subroutine Package for Different Computers | |
| ests0243 | DIGLIB, Multi Platform Graphics Subroutine Library | |
| nea-0625 | DINE, Neutron Flux, Neutron Dose Rate in Multi-Region Slab Reactor Shield by Removal Diffusion | |
| nea-0298 | DISCOUNT-G, Nuclear Power Program with Cost Analysis and Pu Production Optimization | |
| nea-0643 | DISCUS, Neutron Single to Double Scattering Ratio in Inelastic Scattering Experiment by Monte-Carlo | |
| ccc-0170 | DISDOS, Kerma in Model Man from External Gamma Source | |
| ccc-0533 | DISKTRAN, Detector Response to Scalar Flux from DOT-4 Calculation | |
| ccc-0454 | DISPERS, Radioactive Release into Surface Water and Ground Water | |
| nesc0847 | DISPL-1, 2nd Order Nonlinear Partial Differencial Equation System Solution for Kinetics Diffusion Problems | |
| nesc9532 | DISPOSAL_SITE, Low-Level Radioactive Waste Storage Cost Analysis | |
| nesc9618 | DISPPAK SUBPAK, MS FORTRAN Extended Subroutine Library | |
| nea-0184 | DIXY-2, 2-D Homogeneous and Inhomogeneous Neutron Diffusion N X-Z, R-Z, R-Theta Geometry with Perturbation | |
| nea-0391 | DLS, 2-D Diffusion with Line-of-Sight Method for Cavities | |
| iaea1241 | DNTM/R2D, 2-D Transport in X-Y Geometry | |
| csni0071 | DOEL2/SGTR, Steam Generator Tube Rupture incident at the DOEL 2, Westinghouse 2 loop PWR | |
| psr-0155 | DOGS, Flux Plots of Radiation Transport Program Using DISSPLA | |
| psr-0064 | DOMINO, Coupling of Discrete Ordinate Program DOT with Monte-Carlo Program MORSE | |
| iaea0961 | DOMUS, Experimental 2-D Spectra Analysis | |
| ccc-0650 | DOORS, 1-,2-,3-dimensional discrete-ordinates system for deep-penetration neutron and photon transport | |
| psr-0110 | DOQDP ADOQ, Discrete Ordinate Quadrature Generator for Programs DOT and ANISN | |
| nesc1146 | DORIAN, Bayes Method Plant Age Risk Analysis | |
| ccc-0543 | DORT, 1-D 2-D Discrete Ordinate Neutron and Photon Transport with Deep Penetration | |
| ccc-0532 | DORT-PC, 2-D Discrete Ordinates Transport System | |
| nea-1711 | DORTDAT2, Input-Making Support System for a Two-Dimensional SN Code, DORT | |
| ccc-0624 | DOSE-SGTR, Iodine Release During Steam Generator Tube Rupture (SGTR) in PWR | |
| ccc-0536 | DOSEFACTOR-DOE, Dose Rate Conversion Factors for Photon and Electron Exposure | |
| iaea0922 | DOSKMF2, Dose Rate Distribution in Co60 Gamma Irradiation Plants | |
| ccc-0276 | DOT-3.5, 2-D Neutron Transport, Gamma Transport Program DOT with New Space-Scaling | |
| ccc-0320 | DOT-4.2, 2-D Neutron Transport, Gamma Transport with Space Dependent Mesh and Quadrature | |
| nesc9833 | DOT-BPMD, Non Linear Heat Transfer in 2-D Plane or Axisymmetric Structures | |
| ests0599 | DPCT, Probabilistic Deterministic Contaminant Transport in Ground Water | |
| nea-1506 | DPOL3D, 2 Group, 3-D Core Transients and Steady State | |
| uscd1234 | DRAGON 3.05D, Reactor Cell Calculation System with Burnup | |
| ccc-0647 | DRAGON, Reactor Cell Calculation System with Burnup | |
| nea-1412 | DRAWBS, NJOY Graphics Output of ENDF, PENDF, GENDF Data in GKS Format | |
| iaea0885 | DRUCK, Thermal, Mechanical Stress of PWR Fuel Rod During LOCA Blowdown | |
| nea-0215 | DRUCKSCHALE-44, Pressure and Temperature Transients in Blowdown Accident | |
| nea-0839 | DRUFAN-01/MOD2, Transient Thermohydraulics of PWR Primary System LOCA | |
| nea-0457 | DRUGEVO, Time-Dependent Containment Pressure and Temperature in BWR or PWR LOCA | |
| nesc0753 | DRVOCR, Minimization of Nonlinear Function, Variable Metric Method, Derivative Calculation | |
| ests0637 | DSEM, Radioactive Waste Disposal Site Economic Model | |
| nesc0784 | DSNP, Program and Data Library System for Dynamic Simulation of Nuclear Power Plant | |
| psr-0251 | DSNQUAD, Angular Quadrature Weights and Cosines for ANISN | |
| nesc0209 | DTF-4, 1-D MultiGroup Time-Independent Boltzman Equation, Slab, Cylindrical, Spherical Geometry, Sn-Method, Pl-Method | |
| nea-0269 | DTF-G, Reactivity and Flux by 1-D Sn Method on Planar Cylindrical Spherical Geometry | |
| nea-0322 | DTF4-J, 1-D Neutron Transport with Anisotropic Scattering by Sn Method | |
| nea-1671 | DUCT-III, Design Code for Duct-Streaming Radiations | |
| ccc-0453 | DUST, Albedo Monte-Carlo Simulation of Neutron Streaming in Multilegged Square Concrete Ducts | |
| ccc-0634 | DUST-BNL, Radioactive Waste Transport from Container Leaks into Ground Water | |
| nesc0579 | DWARF, 1-D Few-Group Neutron Diffusion with Thermal Feedback for Burnup and Xe Oscillation | |
| nea-1209 | DWBA07/DWBB07, elastic scattering with nucleon-nucleon potential and DWBA for inelastic scattering | |
| ccc-0383 | DWNWND, Downwind Atmospheric Concentration and Dispersion by Gaussian Plume Model | |
| nesc9872 | DWUCK-4/5, Scattering Cross-Sections of Spin 0 and 1/2 and 1 Particles by DWBA | |
| nea-1411 | DYN3D/M2, Reactivity Transients in Light H2O Reactors with Hexagonal Geometry | |
| nesc9910 | DYNA-2D, 2-D Hydrodynamic Finite Elements Method Program with Interactive Rezoning | |
| nesc9909 | DYNA3D, 3-D Finite Elements for Dynamic Response of Inelastic Solids | |
| ests0138 | DYNA3D2000*, Explicit 3-D Hydrodynamic FEM Program | |
| nesc0440 | DYNAM, Once Through Boiling Flow with Steam Superheat, Laplace Transformation | |
| nea-0090 | DYNAMF, Time-Dependent Reactor Dynamics by Laplace Transformation | |
| nea-0217 | DYNAPS, Vibration Analysis of Piping System in Earthquake | |
| ests1300 | E3D, 3-D Elastic Seismic Wave Propagation Code | |
| nea-1564 | EASY-2005.1, European Neutron Activation System | |
| nea-1813 | EASYQAD version 1.0, Visualization for Gamma and Neutron Shielding Calculations | |
| ests0288 | EBQ, Steady-State Space Charge Transport in Cylindrical Geometry | |
| nea-0850 | ECIS-06, Coupled Channel, Statistical Model, Schroedinger and Dirac Equation, Dispersion Relation | |
| ests0219 | ECO2N, a TOUGH2 fluid property module for mixtures of water-NaCl-CO2 | |
| psr-0191 | EDISTR, Nuclear Data Base Generator for Internal Radiation Dosimetry Calculation | |
| nea-0969 | EDMULT-6.4, Electron Depth Dose Distribution in Multilayer Slab Absorbers | |
| nea-0845 | EDO, Doses to Man and Organs from Reactor Operation Noble Gas and Liquid Waste Release | |
| nea-1028 | EDSPA, 1-D Mechanical Displacement for Elastic, Thermoelastic, Viscoelastic Behaviour | |
| nesc9575 | EDTGRAF, DISSPLA User Interface Program | |
| nesc0600 | EGAD, Ground Level Gamma Doses Function of Gamma Energy for Radioactive Releases | |
| ccc-0331 | EGS4, Electron Photon Shower Simulation by Monte-Carlo | |
| nesc0983 | EGUN, Charged Particle Trajectories in Electromagnetic Focusing System | |
| nesc0534 | EISPACK, Subroutines for Eigenvalues, Eigenvectors, Matrix Operations | |
| ccc-0119 | ELBA, Bremsstrahlung Dose from Isotropic Electron Flux on Plane Al Shield | |
| nesc0650 | ELBOW, Stress Analysis, Flexibility Factors for Curved Pipes with Internal Pressure | |
| nesc0881 | ELEFUNT, Testing of Elementary Function Subroutines | |
| nea-1200 | ELEORBIT, 3-D Simulation of Electron Orbits in Magnetic Multipole Plasma Source | |
| nea-0435 | ELIESE-3, Elastic, Inelastic, Reaction Cross-Sections, Polarization, by Hauser-Feshbach | |
| iaea1223 | ELPHIC-PC, Statistical Model Monte-Carlo Simulation of Heavy Ion Nuclear Reactions | |
| ccc-0301 | ELPHO, Muon, Electron, Positron Generator from Pions by Monte-Carlo with HETC Collision Data | |
| nesc0546 | EMERALD, Radiation Release and Dose after PWR Accident for Design Analysis and Operation Analysis | |
| nesc0685 | EMERALD-NORMAL, Routine Radiation Release and Dose for PWR Design Analysis and Operation Analysis | |
| iaea1169 | EMPIRE-II 2.18, Comprehensive Nuclear Model Code, Nucleons, Ions Induced Cross-Sections | |
| uscd1235 | ENDF-UTILITY-CODES, codes to check and standardize data in the Evaluated Nuclear Data File (ENDF) | |
| iaea1402 | ENDVER-ENDVER/GUI, The ENDF File Verification Support Package | |
| uscd1204 | ENSDAT, Evaluated Nuclear Structure Drawings and Tables | |
| uscd1149 | ENSDF ADDGAM, Adds Gammas to Adopted Data Sets | |
| nea-0817 | ENTOSAN, 640 Group Constant Calculation with Resonance from ENDF/B | |
| nea-1686 | ENTREE 1.4.0, BWR Core Simulation System for Space and Time Dependent Coupled Phenomena | |
| iaea1285 | EPICSHOW, Interactive Viewing of EPIC (Electron Photon Interaction Code) Data Library | |
| nesc1143 | EPIPE, Static and Dynamic Piping System Analysis | |
| nesc0675 | EPISODE, 1st Order Stiff or Non-Stiff Ordinary Differencial Equation, Initial Value Problems | |
| nesc0705 | EPISODE-B, 1st Order Stiff or Non-Stiff Ordinary Differencial Equation, Initial Value Problems | |
| nesc0886 | EQ-3 EQ6, Thermodynamics Equilibrium for Aqueous Solution Mineral System | |
| iaea1202 | EQUIVA, Few-Group Diffusion Parameter for PWR Reflector Region by 1-D Transport Calculation | |
| nea-0261 | EQUSTA, Thermodynamics Analysis and Mechanical Analysis for Fast Reactor Accident | |
| nea-1683 | ERANOS 2.0, Modular code and data system for fast reactor neutronics analyses | |
| nea-0458 | ERDBEBEN, Structure Displacements and Forces Under Earthquake Conditions | |
| nea-0534 | EREBUS, Burnup by 2-D MultiGroup Neutron Diffusion with Criticality Search | |
| nesc0601 | ERF/ERFC, Calculation of Error Function, Complementary Error Function, Probability Integrals | |
| nea-0815 | ERINNI, Emission Spectra for Multiple Cascades by Optical Model | |
| nea-0515 | EROS-2, Time-Dependent of Linear System by Inverse Laplace Transformation | |
| nea-1676 | ERRORJ, Multigroup covariance matrices generation from ENDF-6 format | |