| Packages starting with C |
| Package Name | Abstract | RSICC Tapelist | Title |
| CAAC | Abstract | C00476 D0VAX 00 | Code System for Implementation of Atmospheric Dispersion Assessment Required by the Clear Air Act. |
| CAAC | Abstract | C00476 I3033 00 | Code System for Implementation of Atmospheric Dispersion Assessment Required by the Clear Air Act. |
| CACA-2 | Abstract | C00302 I0360 00 | Heavy Isotope and Fission-Product Concentration Calculation Code System. |
| CAD | Abstract | D00059 I0360 00 | 51 Neutron, 25 Gamma-Ray Group ALBEDO DATA Generated with DOT for Various Materials. |
| CADE | Abstract | P00567 MNYCP 00 | Multiple Particle Emission Cross-Sections by Weisskopf-Ewing Theory. |
| CAFDATS | Abstract | P00549 MNYCP 00 | Converter of Angular Fluxes of DORT, ANISN and TORT Systems. |
CALENDF-2010
OECD | Abstract | P00578 PCX86 00 | Pointwise, Multigroup Neutron Cross-Sections and Probability Tables from ENDF/B Evaluations. |
| CALKUX | Abstract | C00594 IBMPC 00 | Code System to Calculate Exposure Transmission of Medical X-ray Beams Through Barrier Materials. |
| CALOR95 | Abstract | C00610 MNYWS 00 | Monte Carlo Code System for Design and Analysis of Calorimeter Systems, Spallation Neutron Source (SNS) Target Systems, etc. |
| CAMERA | Abstract | C00240 C0074 00 | Radiation Transport Analysis Code System and the Computerized Man (CAM) Model. |
| CAMERA | Abstract | C00240 IBMPC 01 | Radiation Transport Analysis Code System and the Computerized Man (CAM) Model. |
| CANDULIB-AECL | Abstract | D00210 MNYCP 00 | Burnup-Dependent ORIGEN-S Cross Section Libraries for CANDU Reactor Fuel Characterization. |
| CAP-88 | Abstract | C00542 D0VAX 00 | Clean Air Act Assessment Package. |
| CAP-88 | Abstract | C00542 I3090 00 | Clean Air Act Assessment Package. |
| CAP-88 | Abstract | C00542 IBMPC 00 | Clean Air Act Assessment Package. |
| CAP88-PC | Abstract | C00542 IBMPC 01 | Clean Air Act Assessment Package. |
| CAPS-2 | Abstract | C00074 CDCMF 00 | Analysis of Structures for Fallout Radiation Shielding. |
| CARL 2.3 | Abstract | C00743 PC586 01 | Code System to Calculate Radiotoxicity, Activity, Dose and Decay Power Calculations for Spent Fuel. |
| CARMEN SYSTEM | Abstract | C00487 U1110 00 | A Code System for Neutronics PWR Calculation by Diffusion Theory with Space-Dependent Feedback Effects. |
| CARNAC | Abstract | C00238 I3691 00 | Calculation of Flux and Neutron Spectra in the Case of Criticality Accident. |
| CARP-82 | Abstract | P00131 I3033 00 | Multigroup Albedo Data Using DOT Angular Flux Results. |
| CARSTEP | Abstract | C00024 I7090 00 | Trajectory and Environment Code-Electron and Proton Fluxes Impinging on Spacecraft in Orbit. |
| CASCADE | Abstract | C00176 C6600 00 | Monte Carlo Simulation of the Transport of High Energy Electrons and Photons in Matter. |
| CASCADE | Abstract | C00176 I0360 00 | Monte Carlo Simulation of the Transport of High Energy Electrons and Photons in Matter. |
| CASIM | Abstract | C00265 I0360 00 | Monte Carlo Simulation of Transport of Hadron Cascades in Bulk Matter. |
| CASK | Abstract | D00023 I3691 04 | 22 Neutron, 18 Gamma-Ray Group, P3, Cross Sections for Shipping Cask Analysis. |
| CASK-81 | Abstract | D00023 IBMPC 06 | 22 Neutron, 18 Gamma-Ray Group, P3, Cross Sections for Shipping Cask Analysis. |
| CASK-81 | Abstract | D00023 I0370 05 | 22 Neutron, 18 Gamma-Ray Group, P3, Cross Sections for Shipping Cask Analysis. |
| CASKCODES | Abstract | P00262 IBMPC 00 | CAPSIZE, SCOPE, AND KWIKDOSE for Shipping Cask Optimization, Dose Calculation, Parameter Evaluation, and Shielding Requirements. |
| CASTHY | Abstract | P00316 FM000 00 | Statistical Model Calculation for Neutron Cross Sections and Capture Gamma-Ray Spectra. |
| CAVEAT | Abstract | C00169 I3675 00 | General Purpose Monte Carlo Time-Dependent Radiation Transport Code in Complex Geometry. |
| CCRMN | Abstract | P00366 MNYCP 00 | Monte Carlo Simulation of the Coupled Transport of Electrons and Photons. |
| CDR | Abstract | C00182 C6600 00 | A Constant Dose Range Code System, Using the LANL-NWEF Neutron-Gamma-Ray Air Flux Tape. |
| CDR | Abstract | C00182 I0360 00 | A Constant Dose Range Code System, Using the LANL-NWEF Neutron-Gamma-Ray Air Flux Tape. |
| CEAR-PPU | Abstract | P00528 PC586 00 | Code System for Monte Carlo Simulation of Detector Pulse Pile Up. |
| CECP-BWR | Abstract | P00370 PC386 00 | Estimating Boiling Water Reactor Decomissioning Costs. |
| CECP-PWR | Abstract | P00371 PC386 00 | Estimating Pressurized Water Reactor Decomissioning Costs. |
| CEM03.03 | Abstract | P00532 MNYCP 01 | Monte-Carlo Code System to Calculate Nuclear Reactions in the Framework of Improved Cascade-Exciton Model. |
CEMENT 1.02
USSO | Abstract | P00412 IBMPC 00 | Computer Code System for the Estimation of Long-Term Performance of Cement-Based Materials. |
| CEPXS | Abstract | C00837 MNYCP 00 | Coupled Electron-Photon Cross Section |
| CEPXS/ONELD 1.0 | Abstract | C00544 MNYCP 02 | One-Dimensional Coupled Electron-Photon Multigroup Discrete Ordinates Code System. |
| CERPI-CEREL | Abstract | P00147 I0360 00 | Code Systems for Automatic Analysis of Gamma-Ray Spectra Obtained with Ge(Li) Detectors. |
| CGS 11.4 | Abstract | P00243 MFMWS 03 | Common Graphics System. |
| CHAINS-PC | Abstract | C00604 IBMPC 00 | Code System to Compute Atom Density of Members of a Single Decay Chain. |
| CHAINT-MC | Abstract | C00584 CYXMP 00 | A Two-Dimensional Model for the Analysis of Contaminant Transport in a Fractured Porous Medium. |
| CHARGE II | Abstract | C00070 C6500 00 | Space Radiation Shielding Code - Proton and Electron Penetration of Multilayered Slabs and Spheres. |
| CHARGE II | Abstract | C00070 I3675 00 | Space Radiation Shielding Code - Proton and Electron Penetration of Multilayered Slabs and Spheres. |
| CHARGE-PC | Abstract | C00070 IBMPC 00 | Space Radiation Shielding Code - Proton and Electron Penetration of Multilayered Slabs and Spheres. |
| CHENDF 7.02 | Abstract | P00333 MNYCP 05 | Codes for Handling ENDF/B-V and ENDF/B-VI Data. |
| CHNSED | Abstract | C00671 I0360 00 | Code System to Model Sediment & Containment Transport. |
| CINDER 1.05 | Abstract | C00755 PC586 00 | Code System for Actinide Transmutation Calculations |
| CITATION-LDI 2 | Abstract | C00643 PC386 02 | Nuclear Reactor Core Analysis Code System. |
| CLAW-IV | Abstract | D00036 I0360 02 | Coupled 30 Neutron, 12 Gamma-Ray Group Cross Sections Based on ENDF/B-IV for Radiation Transport Calculations. |
| CLAW-IV | Abstract | D00036 I3033 03 | Coupled 30 Neutron, 12 Gamma-Ray Group Cross Sections Based on ENDF/B-IV for Radiation Transport Calculations. |
| CLEAR | Abstract | D00042 I3691 00 | 126 Neutron, 36 Gamma-Ray Cross Sections in AMPX and CCCC Interface Formats for LMFBR Neutronics Calculations. |
| CLES | Abstract | D00233 MNYCP 00 | Cross Section Library of Moderator Materials for Low-Energy Neutron Sources. |
| CLOUD-M | Abstract | C00032 I3565 00 | Gamma-Ray Dose Rate from a Radioactive Cloud-Kernel Integration Code. |
| CNCSN 2009 | Abstract | C00726 PCX86 01 | One, Two- and Three-Dimensional Coupled Neutral and Charged Particle SN Parallel Multi-Threaded Code System. |
| COAG-II | Abstract | P00070 I0360 00 | Calculation of the Westcott Epithermal Index and the Westcott 2200 m/s Neutron Flux. |
| COBB | Abstract | D00016 I3675 01 | 123-Group Neutron Cross Section Data Generated from ENDF/B-II Data for Use in the XSDRN Discrete Ordinates Spectral Averaging Code. |
| COBRA-3C-RERTR | Abstract | P00606 I0370 00 | COBRA-3C-RERTR |
| COBRA4I | Abstract | P00419 MNYCP 00 | Code Sytem to Calculate Rod-Bundle and Core Thermal-Hydraulics. |
| COBRA-EN | Abstract | P00507 MNYCP 01 | Thermal-Hydraulic Transient Analysis of Reactor Cores. |
| COBRA-SFS VERSION 6.3 | Abstract | P00614 MNYCP 03 | COBRA-SFS Thermal-Hydraulic Analysis of Multi-Assembly Spent Fuel Storage and Transportation Systems. |
| CODAC (2) | Abstract | P00073 I0360 00 | For TIMOC 72, Monte Carlo Three-Dimensional Neutron Transport Code's Data Generator. |
| COG LIBMAKER | Abstract | P00607 MNYCP 00 | LIBMAKER |
| COG SUPPLEMENTAL LIBRARIES | Abstract | D00271 MNYCP 00 | COG LibMaker – Data Conversion Utility |
| COG11.1 | Abstract | C00829 MNYCP 00 | Multiparticle Monte Carlo Code System for Shielding and Criticality Use. |
| COGAP | Abstract | P00375 MNYCP 01 | Nuclear Power Plant Containment Hydrogen Control System Evaluation Code. |
| COHORT-II | Abstract | C00198 I7094 00 | General Purpose Monte Carlo Radiation Transport Code System. |
| COLLIMATOR | Abstract | C00136 I7090 00 | Monte Carlo Calculation of the Spectrum of Gamma Radiation from a Collimated Co-60 Source. |
| COLUMN2 | Abstract | C00534 ALLMF 00 | Calculation of Effects of Physicochemical Processes on Migration. |
| COMAND | Abstract | P00091 I0360 00 | A Multigroup ANISN Cross Section Data Library Collapsing Code System. |
| COMBINE-PC | Abstract | P00286 IBMPC 00 | Code System to Compute Neutron Spectra and ENDF/B Version 5 Based Multigroup Neutron Constants. |
| COMIDA | Abstract | P00343 MNYCP 00 | Radionuclide Food Chain Model for Acute Fallout Deposition. |
COMMIX-1B
USSO | Abstract | P00393 DVX11 00 | 3-D Single-Phase Thermal Hydraulics |
COMMIX-1B
USSO | Abstract | P00393 I3033 00 | 3-D Single-Phase Thermal Hydraulics |
COMMIX-1C
USSO | Abstract | P00393 MNYCP 00 | 3-D Single-Phase Thermal Hydraulics |
| COMNUC3B | Abstract | P00302 CYXMP 00 | A Compound Nucleus Analysis Program. |
| COMPAR | Abstract | P00240 C0170 00 | Compares Multigroup Cross Sections Generated by NJOY, GROUPIE, FLANGE-II, ETOG-3 and XLACS. |
| COMPARE-MOD1A | Abstract | P00410 C7600 00 | Code System to Calculate Transient Flow With Heat Sinks & Doors. |
| COMPARE-MOD1A | Abstract | P00410 I3033 00 | Code System to Calculate Transient Flow With Heat Sinks & Doors. |
| COMPASS 1.0.0 | Abstract | P00520 PC586 00 | Computerization of MARSSIM for Planning and Assessing Site Surveys. |
| COMPBRN3 | Abstract | P00389 PC386 00 | Code System for Modeling Compartment Fires. |
| COMPLOT | Abstract | P00259 IBMMF 00 | Convert EXFOR Format Data to Computation Format and Plot Comparisons of EXFOR and ENDF/B Evaluated Data (Version 86-1). |
| COMPRASH | Abstract | C00072 I3675 00 | Spinney Removal-Diffusion Shielding Code. |
| COMRADEX4 | Abstract | C00332 I0360 00 | Evaluator of Potential Radiological Doses in the Near (< 10 km) Environment of Radioactive Release. |
| CONDOR-3 | Abstract | C00811 I0370 00 | Two-Dimensional Reactor Program with Local and Spectrum Dependent Burnup. |
| CONDOS-II | Abstract | C00416 I0360 00 | Code for Estimating Radiation Doses from Radionuclide-Containing Consumer Products. |
| CONFOLD | Abstract | P00053 C6600 00 | Least-Structure Unfolding Code System for Measured Neutron and Gamma-Ray Spectra. |
| CONFOLD | Abstract | P00053 I0360 00 | Least-Structure Unfolding Code System for Measured Neutron and Gamma-Ray Spectra. |
| CONSTRIP V | Abstract | C00139 I3675 00 | Vertical Barrier-Finite Source Plane Gamma-Ray Penetration Code System. |
| CONTEMPT4 | Abstract | P00397 MNYCP 00 | Code System for PWR & BWR Multicompartment Containment Analysis. |
CONTEMPT-LT28B
USSO | Abstract | P00387 C7600 00 | Code System to Predict Containment Pressure-Temperature Response To a Loss-Of-Coolant Accident. |
| CONVERT | Abstract | P00036 C6600 00 | An IBM-to-CDC Program Conversion Code. |
| COOL-C | Abstract | P00017 I0360 00 | Spectra Unfolding Codes. |
| CORTES | Abstract | P00404 I0360 00 | Code System for Thermal & Mechanical Analysis of Tees. |
| COV-15GROUP-2006 | Abstract | D00232 MNYCP 00 | 15-Group Cross Section Covariance Matrix Library. |
| COVERV | Abstract | D00077 I0360 01 | Compilation of Multigroup Cross-Section Covariance Matrices in COVERX Format for Several Important Materials. |
| COVERX | Abstract | D00044 I0360 02 | Compilation of Multigroup Cross-Section Covariance Matrices in COVERX Format for Several Important Materials. |
| COVFILS | Abstract | D00091 I0360 00 | Neutron Data and Covariances for Sensitivity and Uncertainty Analysis. |
| COVFILS-2 | Abstract | D00137 ALLCP 00 | Neutron Data and Covariances for Sensitivity and Uncertainty Analysis. |
| CRAC2 | Abstract | C00419 C0000 00 | Code System for Calculating Reactor Accident Consequences. |
| CRAC2 | Abstract | C00419 I3033 00 | Code System for Calculating Reactor Accident Consequences. |
| CRECTJ5 | Abstract | P00250 D0780 00 | A Computer Program for Compilation of Evaluated Nuclear Data in ENDF/B Format. |
| CRESO | Abstract | P00184 I3081 00 | Resonance Data-Handling Code System. |
| CRRIS | Abstract | C00518 I3033 00 | Computerized Radiological Risk Investigation System for Assessing Doses and Health Risks from Atmospheric Releases of Radionuclides. |
| CRRIS | Abstract | C00518 PC586 00 | Computerized Radiological Risk Investigation System for Assessing Doses and Health Risks from Atmospheric Releases of Radionuclides. |
| CRYO-S(A,B)-ACE1 | Abstract | D00253 MNYCP 00 | Scattering Law and Continuous Energy Cross Section Library of Materials at Cryogenic Temperatures. |
| CRYSTAL BALL | Abstract | C00233 C6600 00 | Code System for Determining Neutron Spectra from Activation Measurements. |
| CRYSTAL BALL | Abstract | C00233 I0360 00 | Code System for Determining Neutron Spectra from Activation Measurements. |
| CTF | Abstract | C00871 PCX86 00 | CTF is the modernized version of the legacy subchannel thermal hydraulics (TH) code COBRA-TF |
| CTR DATA | Abstract | D00028 I3675 01 | 73-Group P3 Coupled Neutron and Gamma-Ray Cross Sections for Fusion Reactor Calculations. |
| CUPED | Abstract | P00032 I3675 00 | Scintillation Spectrometer Polyenergetic Gamma Photon Experimental Distributions Unfolding Code. |
| CYGAS | Abstract | C00317 I3033 00 | A Gamma-Ray Attenuation Code System for Large Gamma-Ray Sources Shielded by Coaxial Cylinders. |
| CYGNUS-C SPHERE | Abstract | C00232 I0360 00 | Monte Carlo Neutron Transport Code System in Spherical Geometry. |
| CYLDOS | Abstract | C00389 I0360 00 | A Cylindrical Geometry Gamma-Ray Flux Attenuation Code System. |