| Packages with Keyword: MICROCOMPUTER |
| Package Name | Abstract | RSICC Tapelist | Title |
| 1DB-2DB-3DB | Abstract | C00741 PC586 00 | One-Dimensional Diffusion Code System for Nuclear Reactor. |
| ABAREX | Abstract | P00248 MNYCP 01 | Neutron Spherical Optical-Statistical Model Code System. |
| ABBN-90 | Abstract | D00182 MNYCP 00 | Multigroup Constant Set for Calculation of Neutron and Photon Radiation Fields and Functionals, Including the CONSYST2 Program. |
| ACTIV-PC | Abstract | P00287 IBMPC 00 | A Program to Process Gamma or X-ray Spectra. |
| ADASAGE | Abstract | P00426 IBMPC 00 | Ada Application Development System. |
| ALBEDO/ALBEZ | Abstract | C00555 IBMPC 00 | Calculates Attenuation of Radiation in Single and Double Bends. |
| ALDOSE | Abstract | C00577 IBMPC 00 | Dose Calculation for Alpha Disc Source. |
| ALKASYS-PC | Abstract | C00558 IBMPC 00 | A Computer Program For Studies of Rankine-Cycle Space Nuclear Power Systems. |
| ALPHN | Abstract | C00612 IBMPC 00 | Code System for Calculating (alpha,n) Neutron Production in Canisters of High-Level Waste. |
| ANA | Abstract | P00356 IBMPC 00 | Code System for Gamma-Ray Spectra Analyses. |
| ANISN-ORNL | Abstract | C00254 MNYCP 02 | One-Dimensional Discrete Ordinates Transport Code System with Anisotropic Scattering. |
| ANS643 | Abstract | D00129 IBMPC 02 | Geometric Progression Gamma-Ray Buildup Factor Coefficients. |
| APUD 3.0 | Abstract | C00637 IBMPC 00 | Code System for Analyzing, Predicting Consequences of, and Guiding the Response to Nuclear Emergencies. |
| AXMIX-PC | Abstract | P00297 IBMPC 00 | ANISN Cross Section Code System. |
| BASACF | Abstract | P00285 IBMPC 00 | Bayesian Approach to Spectrum Adjustment with Covariance Filter. |
| BETA-S 6 | Abstract | C00657 MNYCP 01 | Code System to Calculate Multigroup Beta-Ray Spectra. |
| BLOCKAGE V2.5R | Abstract | P00377 IBMPC 00 | Code System to Calculate Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in a BWR. |
BLT-FEMWATER
USSO | Abstract | C00633 PC386 00 | Code System to Solve for Release and Transport of Contaminants through Saturated/Unsaturated Media. |
| BUCORST | Abstract | P00339 PC386 00 | A Code to Prepare Burnup-Dependent Multigroup Nuclear Reactor Source Terms. |
| BUGLE-80 | Abstract | D00075 IBMPC 03 | Coupled Neutron, Gamma-Ray Group Cross Section Library Derived from ENDF/B-VI for LWR Shielding and Pressure Vessel Dosimetry Applications. |
| BUGLE-80 | Abstract | D00075 PC386 01 | Coupled Neutron, Gamma-Ray Group Cross Section Library Derived from ENDF/B-VI for LWR Shielding and Pressure Vessel Dosimetry Applications. |
| CALKUX | Abstract | C00594 IBMPC 00 | Code System to Calculate Exposure Transmission of Medical X-ray Beams Through Barrier Materials. |
| 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. |
| 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. |
| CASK | Abstract | D00023 I3691 04 | 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. |
| CASK-81 | Abstract | D00023 IBMPC 06 | 22 Neutron, 18 Gamma-Ray Group, P3, Cross Sections for Shipping Cask Analysis. |
| CEPXS/ONELD 1.0 | Abstract | C00544 MNYCP 02 | One-Dimensional Coupled Electron-Photon Multigroup Discrete Ordinates Code System. |
| CHAINS-PC | Abstract | C00604 IBMPC 00 | Code System to Compute Atom Density of Members of a Single Decay Chain. |
| 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. |
| CITATION-LDI 2 | Abstract | C00643 PC386 02 | Nuclear Reactor Core Analysis 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. |
| COMPASS 1.0.0 | Abstract | P00520 PC586 00 | Computerization of MARSSIM for Planning and Assessing Site Surveys. |
| 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. |
| DCHAIN 1.3 | Abstract | C00640 MNYCP 01 | Code System for Radioactive Decay and Reaction Chain Calculations. |
| DCTDOS | Abstract | C00520 IBMPC 00 | Neutron and Gamma-Ray Penetration in Composite Duct Systems. |
| DECDC 1.0 | Abstract | D00213 MNYCP 00 | Nucear Decay Data Files for Radiation Dosimetry Calculations. |
| DETAN 95 | Abstract | P00361 MNYCP 00 | Code System to Calculate Spectrum-Averaged Cross Sections and Detector Responses in Neutron Spectra. |
| DIAMANT2 | Abstract | C00414 PC386 00 | Multigroup Two-Dimensional Discrete Ordinates Transport Code System for Triangular Geometry, Release 2.0. |
| DIFBAS | Abstract | P00334 MNYCP 00 | A Bayesian Approach to Unfolding a Neutron Spectrum from a Spectrum of Recoiled Protons. |
| DIMEN | Abstract | P00341 IBMPC 00 | Code System for Isotope Identification by Gamma-Ray Analysis. |
| DOMUS | Abstract | P00301 IPCXT 00 | A Program for Decomposing A Two-Dimensional Spectrum. |
| DOSE-SGTR | Abstract | C00624 IBMPC 00 | Code System to Calculate the Integrated Iodine Release to the Environment During a Steam Generator Tube Rupture in a PWR. |
| DUST-BNL | Abstract | C00634 PC386 00 | Disposal Unit Source Term by One-Dimensional, Transient, Finite-Difference, Subsurface Release and Transport of Contaminants. |
| EGS4 | Abstract | C00331 MNYCP 00 | Monte Carlo Simulation of the Coupled Transport of Electrons and Photons. |
| EQUIVA-1.1 | Abstract | P00323 IMFPC 00 | Generation of Environment-Insensitive Equivalent Diffusion Theory Parameters for PWR Reflector Regions. |
| EQUIVA-2 | Abstract | P00324 IMFPC 00 | Generation of Environment-Insensitive Equivalent Diffusion Theory Parameters for PWR Reflector Regions. |
| FASTPLOT 1.0 | Abstract | P00354 IBMPC 00 | Interface to Microsoft FORTRAN Graphics. |
| FCXSEC | Abstract | D00085 PC386 01 | 22 Neutron, 21 Gamma-Ray Group Cross Section Libraries in ANISN Format for Nuclear Fuel Cycle Shielding Calculations. |
| FDMXPC | Abstract | P00322 IPCAT 00 | Code System for Calculation of Neutron Transmission and Other Functionals from Evaluated Data in ENDF Format. |
| FEDGROUP-R | Abstract | P00349 MNYCP 00 | Code System for Processing Evaluated Nuclear in ENDF/B, KEDAK or UKNDL Formats into Constants for Reactor Physics Calculation. |
| FEMWASTE/FEMWATER | Abstract | C00451 C7600 00 | A Finite-Element Model of Waste and Water Transport through Porous Saturated-Unsaturated Media. |
| FEMWASTE/FEMWATER | Abstract | C00451 PC386 00 | A Finite-Element Model of Waste and Water Transport through Porous Saturated-Unsaturated Media. |
| FERD-PC | Abstract | P00273 IBMPC 00 | Interactive Multichannel Neutron and Gamma-Ray Spectrum Matrix Unfolding Code System. |
| FLYSPEC-SHORTS | Abstract | P00196 C7600 00 | Neutron Unfolding Code System for Reducing Proton-Recoil Pulse-Height Obtained with NE-213 Liquid Scintillator. |
| FPZD | Abstract | C00603 PC386 00 | Code System for Multigroup Neutron Diffusion/Depletion Calculations. |
| FRANCO | Abstract | P00363 MNYCP 00 | Finite Element Fuel Rod Analysis Code System. |
| GCI | Abstract | P00421 IBMPC 00 | Generic Communications Index |
| GENII 2.10 | Abstract | C00737 PCX86 02 | Environmental Radiation Dosimetry Software System. |
| GGG-GP | Abstract | C00564 IBMPC 00 | Kernel Integration Code System - Multigroup Gamma-Ray Scattering Using the GP Buildup Factor. |
| GIP | Abstract | P00229 IBMPC 00 | Group-Organized Cross-Section Input Program. |
| GMA | Abstract | P00367 MNYCP 00 | Code System for Calculation of Reactor Accident Consequences. |
| GNOMER | Abstract | C00625 MNYCP 01 | Multigroup 3-Dimensional Neutron Diffusion Nodal Code System with Thermohydraulic Feedbacks. |
| GUI2QAD-3D | Abstract | C00697 PC586 01 | A Graphical User Interface for QAD-CGPIC, a Point Kernal Code for Neutron and Gamma-Ray Shielding Calculations in Complex Geometry. |
| HABIT 1.1 | Abstract | C00665 IBMPC 01 | Code System for Evaluation of Control Room Habitability. |
| HEATING 7.3 | Abstract | P00199 MNYCP 06 | Multidimensional, Finite-Difference Heat Conduction Analysis Code System. |
| HILO86 | Abstract | D00119 I0360 00 | Group Cross Sections for Radiation Transport |
| HILO86 | Abstract | D00119 PC386 01 | Group Cross Sections for Radiation Transport |
| HILO86R | Abstract | D00187 ALLCP 00 | Group Cross Sections for Radiation Transport |
| HOTSPOT 3.0.2 | Abstract | M00009 IBMPC 03 | Health Physics Code System for Evaluating Accidents Involving Radioactive Materials. |
| HPPOS 1.5 | Abstract | D00173 IBMPC 00 | Health Physics Position Database. |
| HPPOS V2 | Abstract | D00173 IBMPC 01 | Health Physics Position Database. |
| ICAR | Abstract | P00291 IPCAT 00 | A Code For Combinatorial Calculation of Level Densities. |
| ICOM | Abstract | C00651 PC386 00 | Code System for Calculating Ion Track Condensed Collision Model. |
| INFLTB | Abstract | P00313 ALLCP 00 | Gamma-Ray Absorption Coefficient Calculation. |
| IRDAM | Abstract | C00524 IPCXT 00 | Interactive Rapid Dose Assessment Model. |
| ISO-PC 2.1 | Abstract | C00636 IBMPC 01 | Kernel Integration Code System for General Purpose Isotope Shielding Analyses. |
| KENO2MCNP | Abstract | P00541 PC586 00 | Conversion of Input Data between KENO V.a and MCNP File Formats. |
| KUX | Abstract | C00515 ALLCP 00 | Medical X-Ray Shielding Calculation. |
| LABAN-PEL | Abstract | C00611 IMFPC 00 | A Two-Dimensional, Multigroup Diffusion, High-Order Response Matrix Code. |
| LINEDOSE | Abstract | C00468 IBMPC 00 | A Line Source Shielding Code for Personal Computers. |
| LPTAU | Abstract | P00340 MNYCP 00 | Quasi-Random Sequence Generators. |
| LSHINSE | Abstract | C00554 IBMPC 00 | Calculates Flux and Dose Rate from the Scattering of Radiation in Air. |
| LSL-M2 | Abstract | P00233 D6220 00 | Least-Squares Logarithmic Adjustment of Neutron Spectra. |
| LSL-M2 | Abstract | P00233 IBMPC 00 | Least-Squares Logarithmic Adjustment of Neutron Spectra. |
| LSMOD-GLSMOD | Abstract | P00342 IBMPC 00 | A Least-Squares Computational Tool Kit. |
| LTC | Abstract | P00329 IBMPC 00 | LMR Transient Calculation Code System. |
| MARLOWE 15B | Abstract | P00137 MNYCP 08 | Computer Simulation of Atomic Collisions in Crystalline Solids. |
| MARMER | Abstract | C00579 D8350 00 | A Flexible Point-Kernel Shielding Code System. |
| MARMER | Abstract | C00579 PC486 00 | A Flexible Point-Kernel Shielding Code System. |
MCNP-DSP-EXE
810 | Abstract | C00699 MNYCP 01 | Monte Carlo N-Particle Transport Code System with Digital Signal Processing based on MCNP4A. |
MCNPX-POLIMI-EXE
810 | Abstract | C00791 MNYCP 01 | Monte Carlo N-Particle Transport Code System To Simulate Time-Analysis Quantities. |
| MCRAC | Abstract | C00562 IBMPC 00 | Multiple Cycle Reactor Analysis Code. |
| MICROX-2 | Abstract | P00374 MNYCP 02 | Code System to Create Broad-Group Cross Sections with Resonance Interference and Self-Shielding from Fine-Group and Pointwise Cross Sections. |
| MILDOS-AREA | Abstract | C00608 IBMPC 00 | Calculation of Radiation Dose from Uranium Recovery Operations for Large-Area Sources. |
| MOCA | Abstract | C00590 IPCAT 00 | Monte Carlo Criticality Code System for Hexagonal Geometries. |
| MONTEBURNS 2.0 | Abstract | P00455 MNYCP 02 | Automated, Multi-Step Monte Carlo Burnup Code System. |
| MORSE-CGA | Abstract | C00474 ALLCP 03 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MORSE-EMP | Abstract | C00588 IBMPC 00 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
MRIPP 1.0
810 | Abstract | C00655 PC386 00 | Magnetic Resonance Image Phantom Code System to Calibrate in vivo Measurement Systems. |
| MSM-SOURCE | Abstract | P00369 MNYCP 00 | Code System for Generation of Input Data for MCNP. |
| NAC | Abstract | C00164 C0000 00 | Neutron Activation Analysis and Product Isotope Inventory Code System. |
| NAC | Abstract | C00164 IBMMF 00 | Neutron Activation Analysis and Product Isotope Inventory Code System. |
| NAC-PC | Abstract | C00164 IBMPC 00 | Neutron Activation Analysis and Product Isotope Inventory Code System. |
| NCRP49 | Abstract | C00462 IBMPC 00 | X-Ray Shield Calculation System. |
| NJOY97.0 | Abstract | P00368 MNYCP 00 | Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data. |
| NJOY99.0 | Abstract | P00480 MNYCP 00 | Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data. |
| NUCDECAY | Abstract | D00172 PC386 01 | Nuclear Decay Data for Radiation Dosimetry Calculations for ICRP and MIRD. |
| NUCDECAYCALC | Abstract | D00202 PC586 00 | Nuclear Decay Data for Radiation Dosimetry Calculations for ICRP. |
| ORIGEN2.2 | Abstract | C00371 ALLCP 03 | Isotope Generation and Depletion Code - Matrix Exponential Method. |
| ORIGEN-JENDL32 | Abstract | C00703 MNYWS 00 | Isotope Generation and Depletion Code - Matrix Exponential Method. |
| ORMONTE | Abstract | P00275 IBMPC 00 | Uncertainty Analysis Code System for Use with User-Developed Systems Models. |
| ORPLOT-PC | Abstract | P00328 PC386 00 | Plotting Package for Data Evaluation Intercomparison. |
| PAGAN | Abstract | C00621 IBMPC 00 | Code System for Performance Assessment Ground-water Analysis for Low-level Nuclear Waste. |
| PARET-ANL | Abstract | P00516 MNYCP 00 | Code System to Predict Consequences of Nondestructive Accidents in Research and Test Reactor Cores. |
| PARET-ANL(NESC) | Abstract | P00565 MNYCP 00 | Code System to Predict Consequences of Nondestructive Accidents in Research and Test Reactor Cores. |
| PART61 | Abstract | C00499 IBMPC 01 | Low-Level Radioactive Waste Impacts Analysis System. |
| PEGAS | Abstract | P00336 IBMPC 00 | Pre-Equilibrium-Equilibrium Gamma-and-Spin Code System. |
| PEQAG-2 | Abstract | P00293 IPCAT 00 | A Pre-equilibrium Computer Code With Gamma Emission. |
| PHOTX | Abstract | D00136 D0VAX 01 | Photon Interaction Cross Section Library. |
| PHOTX | Abstract | D00136 IBMPC 00 | Photon Interaction Cross Section Library. |
| PLOTTAB-89.1 | Abstract | P00274 ALLCP 00 | Plot Continuous Curves or Discrete Points. |
| PRE-ANISN | Abstract | P00332 PC386 00 | A Preprocessing Code for ANISN and Other Radiation Transport Codes. |
| PR-EDB | Abstract | D00196 IBMPC 03 | Power Reactor Embrittlement Data Base. |
| PRISIM | Abstract | C00574 IBMPC 00 | Plant Risk Status Information Management System. |
| PSU-LEOPARD/RBI | Abstract | C00563 IBMPC 01 | A Spectrum Dependent Non-Spatial Depletion Code. |
| PTRAN | Abstract | C00618 PC386 00 | Proton Monte Carlo Transport Program for the PC. |
| QAD-CGGP-A | Abstract | C00645 MNYCP 00 | Kernel Integration Code System. |
| QADMOD-GP | Abstract | C00565 IBMPC 00 | Point Kernel Gamma-Ray Shielding Code With Geometric Progression Buildup Factors. |
| QBF | Abstract | C00617 PC386 00 | Code System to Calculate Radiation Dose Rates Relative to Spent Fuel Shipping Casks. |
| QBSHIELD | Abstract | C00599 IBMPC 00 | Spherical Shield Design for Gamma-Ray Sources Using the Buildup Factor Method. |
| QUINCE-PC | Abstract | C00556 IBMPC 00 | Calculates Absorbed Dose From Skin Contamination. |
| RADAC | Abstract | C00627 PC486 02 | Code System for Calculating Radioactive Decay and Accumulation of Decayed Products Using Integer-Array Arithmetic for Precise Evaluation of the Bateman Equations. |
| RADCOMPT 2.10L | Abstract | P00348 IBMPC 00 | Sample Analysis Code System for the Dual Channel Counter. |
| RASCAL 4.3 | Abstract | C00783 PCX86 02 | Radiological Assessment for Consequence Analysis. |
| RBD | Abstract | C00632 IBMPC 00 | U.S. Army Radiological Bioassay and Dosimetry. |
| RCSLK9 | Abstract | P00452 IBMPC 00 | Code System to Calculate Reactor Coolant System Leak Rate. |
| REAC*3 | Abstract | C00443 IBMPC 00 | Computer Code System for Activation and Transmutation. |
| REAC*3 | Abstract | C00443 MFMWS 00 | Computer Code System for Activation and Transmutation. |
| REACTION | Abstract | P00347 AL000 00 | Code System to Calculate Integral Parameters with Reaction Rates from WIMS Output. |
| REACTION | Abstract | P00347 IBMPC 00 | Code System to Calculate Integral Parameters with Reaction Rates from WIMS Output. |
| REBUS3/VARIANT8 | Abstract | C00653 MNYWS 01 | Code System for Analysis of Fast Reactor Fuel Cycles. |
| REPRISK PC 1.02 | Abstract | C00586 PC386 01 | Repository Risk Assessment Software for Personal Computers. |
RISKIND 2.0
FEDC | Abstract | C00623 IBMPC 02 | Radiological Risk Assessment Code System for Spent Nuclear Fuel Transportation. |
| RIVER-RAD | Abstract | C00626 MNYCP 00 | Code System for Simulating the Transport of Radionuclides in Rivers. |
| RSAC-7.2 | Abstract | C00761 PC586 01 | Radiological Safety Analysis. |
| SAILOR | Abstract | D00076 PC386 01 | Coupled, Self-Shielded, 47 Neutron, 20 Gamma-Ray, P3, Cross Section Library for Light Water Reactors. |
| SAIPS-PC | Abstract | P00295 IBMPC 00 | Information Processing System for Calculating Neutron Spectra from Measured Reaction Rates. |
| SAND-II | Abstract | C00112 MNYCP 03 | Neutron Flux Spectra Determination by Multiple Foil Activation Method. |
| SCAT-2 | Abstract | P00294 MNYCP 03 | Code System for Calculating Total and Elastic Scattering Cross Sections Based on an Optical Model of the Spherical Nucleus. |
| SESOIL | Abstract | C00629 IBMPC 03 | Code System to Calculate One-Dimensional Vertical Transport for the Unsaturated Soil Zone. |
| SHIELDOSE | Abstract | C00379 ALLMF 00 | Code System for Space Shielding Radiation Dose Calculations. |
| SHIELDOSE-PC | Abstract | C00379 IBMPC 00 | Code System for Space Shielding Radiation Dose Calculations. |
| SIGMA II | Abstract | C00118 C6000 00 | Space Radiation Dose Analysis Within Complex Configurations. |
| SIGMA II | Abstract | C00118 PC486 00 | Space Radiation Dose Analysis Within Complex Configurations. |
| SIGMA-A | Abstract | D00139 ALLMF 00 | Photon Interaction and Absorption Cross Sections. |
| SIGMA-A | Abstract | D00139 IBMPC 00 | Photon Interaction and Absorption Cross Sections. |
| SKYDATA-KSU | Abstract | D00188 IBMPC 00 | Parameters for Approximate Neutron and Gamma-Ray Skyshine Response Functions and Ground Correction Factors. |
| SKYIII-PC | Abstract | C00289 IBMPC 01 | Calculation of the Effects of Structure Design on Neutron, Primary Gamma-Ray and Secondary Gamma-Ray Dose Rates in Air. |
| SKYSHINE-III | Abstract | C00289 D0VAX 00 | Calculation of the Effects of Structure Design on Neutron, Primary Gamma-Ray and Secondary Gamma-Ray Dose Rates in Air. |
| SKYSHINE-KSU | Abstract | C00646 IBMPC 03 | Calculation of the Effects of Structure Design on Neutron, Primary Gamma-Ray and Secondary Gamma-Ray Dose Rates in Air. |
| SLIDERULE 1.0 | Abstract | C00704 PC586 01 | Nuclear Criticality Slide Rule. |
| SMART | Abstract | C00602 ALLCP 00 | Code System for Calculating Early Offsite Consequences from Nuclear Reactor Accidents. |
| SOURCES-4C | Abstract | C00661 MNYCP 04 | Code System for Calculating (alpha,n), Spontaneous Fission, and Delayed Neutron Sources and Spectra. |
| STAPREF | Abstract | P00498 PC586 00 | Code System to Calculate Nuclear Reaction Cross Sections by Evaporation Model. |
| STAPRE-H95 | Abstract | P00325 MNYCP 01 | Code System to Calculate Energy-Averaged Cross Sections of Particle Induced Nuclear Reactions. |
| STAR CODES | Abstract | P00330 IBMPC 00 | Code System for Calculating Stopping-Power and Range Tables for Electrons, Protons, and Helium Ions. |
| SUPERDAN-PC | Abstract | P00282 IBMPC 00 | Calculates Dancoff Factor of Spheres, Cylinders and Slabs. |
| TART2022 | Abstract | C00638 MNYCP 09 | Coupled Neutron-Photon, 3-D, Combinatorial Geometry, Time Dependent, Monte Carlo Transport Code System. |
| TIBSO | Abstract | C00512 MNYCP 00 | Code System to Calculate Production and Migration of Radionuclides in Nuclear Reactor Systems. |
| TRIGAP | Abstract | C00600 IBMPC 00 | A Computer Code for TRIGA Type Reactors. |
| UKFY2 | Abstract | D00171 IBMPC 00 | UK Fission Product Yield Library. |
| UPEAK | Abstract | P00300 IPCXT 00 | A Program for Decomposing A One-Dimensional Spectrum. |
| UPEML 3.0 | Abstract | P00245 ALLCP 01 | A Machine-Portable CDC UPDATE Emulator. |
| VALE 1.1 | Abstract | C00613 IRISC 01 | A Multigroup Diffusion Theory Neutronics Code System for Solving Two- and Three-Dimensional Problems for Triagonal Geometries. |
| VALE 1.1 | Abstract | C00613 PC386 01 | A Multigroup Diffusion Theory Neutronics Code System for Solving Two- and Three-Dimensional Problems for Triagonal Geometries. |
| VENTURE-PC | Abstract | C00654 PC586 02 | A Reactor Analysis Code System. |
| VESTA 2.1.5-AURORA 1.0 | Abstract | C00769 PCX86 01 | A Generic Monte Carlo Code and Depletion Module Interface. |
| VIDEO-PC | Abstract | P00311 IBMPC 00 | Super VGA Primitives Graphics System. |
| VPI-NECM | Abstract | C00481 C0740 00 | Nuclear Engineering Computer Models for In-Core Fuel Management Analysis. |
| VPI-NECM | Abstract | C00481 D0VAX 00 | Nuclear Engineering Computer Models for In-Core Fuel Management Analysis. |
| VPI-NECM | Abstract | C00481 PC486 00 | Nuclear Engineering Computer Models for In-Core Fuel Management Analysis. |
| WILIT | Abstract | P00344 MNYCP 00 | A Utility Program for WIMS Libraries. |
| WIMSD-5B.12 | Abstract | C00656 MNYCP 02 | Deterministic Code System for Reactor Lattice Calculation |
| XCOM | Abstract | D00174 IBMPC 00 | Photon Cross Sections on a Personal Computer. |
| XG-IAEA | Abstract | D00163 IBMPC 00 | X-ray and Gamma-ray Standards For Detector Calibration. |
| XPORT-PC | Abstract | C00559 IBMPC 00 | An Approximation For Black Body X-Ray Transport in Air. |
| XSHLD | Abstract | C00495 IBMPC 00 | Diagnostic X-Ray Shielding Calculation. |
| ZOTT99 | Abstract | P00272 ALLCP 02 | Zero-in On The Truth; Evaluation of Correlated Data Using Partitioned Least Squares. |
| ZYLIND-PC | Abstract | C00557 IBMPC 00 | An Interactive Point Kernel Program For Photon Dose Rate Prediction of Cylindrical Source/Shield Arrangements. |