| Packages starting with P |
| Package Name | Abstract | RSICC Tapelist | Title |
| PABLM | Abstract | C00402 U1100 00 | Calculation of Accumulated Radiation Doses to Man from Radionuclides Found in Food Products and from Radionuclides in the Environment. |
| PADF-2007 | Abstract | D00259 PCX86 00 | Proton Activation Data File in ENDF-6 Format. |
| PADLOC | Abstract | C00330 U0000 00 | A One-Dimensional, Time-Dependent Program for Calculating Coolant and Plateout Fission Product Concentrations in a Network of Pipes. |
| PAGAN | Abstract | C00621 IBMPC 00 | Code System for Performance Assessment Ground-water Analysis for Low-level Nuclear Waste. |
| PALLAS-1D(VII) | Abstract | C00380 FM380 00 | Multigroup Time-Independent Neutron Transport Code System for Plane or Spherical Geometry. |
| PALLAS-2DCY-FX | Abstract | C00391 FM380 00 | Multigroup Time-Independent Neutron Transport Code System for Plane or Spherical Geometry. |
| PAPER 1 | Abstract | P00097 C6600 00 | Monte Carlo Calculation of Solid Angle and Self-Absorption Factors for an Inclined Cylindrical Source Viewed by a Cylindrical Detector. |
| PAPIN | Abstract | P00156 I0370 00 | A Code System to Calculate Cross Section Probability Tables, Bondarenko and Transmission Self-Shielding Factors for Fertile Isotopes in the Unresolved Resonance Region. |
| 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. |
| PARTISN 8.29 | Abstract | C00842 MNYCP 00 | Time-Dependent, Parallel Neutral Particle Transport Code System. |
| PATCH-7 | Abstract | C00243 C0074 00 | Three-Dimensional Kernel Integration Code-Explicit Single Scattering Option. |
| PAVAN | Abstract | C00445 I3033 00 | Atmospheric Dispersion Code System for Evaluating Accidental Radioactivity Releases from Nuclear Power Stations. |
| P-CARES | Abstract | P00538 PC586 00 | Probabilistic Computer Analysis for Rapid Evaluation of Structures. |
| PC-BATLE | Abstract | P00451 IBMPC 00 | Code System to Calculate Brief Adversary Threat Loss Estimate. |
| PCC/SRC | Abstract | P00456 D0VAX 00 | Code System to Calculate Correlation & Regression Coefficients. |
| PC-PRAISE | Abstract | P00391 IBMPC 00 | Code System for Analysis of Piping Reliability Including Seismic Events. |
| PEFPYD | Abstract | D00096 ALLMF 02 | Aggregate Fission-Product Decay Data Based on ENDF/B-IV and -V. |
| PEGAS | Abstract | P00336 IBMPC 00 | Pre-Equilibrium-Equilibrium Gamma-and-Spin Code System. |
| PELE-1C | Abstract | P00461 C7600 00 | Code System for Fluid-Structure Interaction Analysis. |
| PELINOMIC-3A | Abstract | P00596 I0370 00 | Power Plant Cost Optimization for Dispersed Load Centers. |
| PELINSCA | Abstract | P00168 I0360 00 | A Code System for Nuclear Elastic and Inelastic Scattering Calculations. |
| PELSHIE | Abstract | C00202 C0000 00 | General Purpose Kernel Integration Shielding Code System-Point and Extended Gamma-Ray Sources. |
| PELSHIE3 | Abstract | C00202 IBMMF 00 | General Purpose Kernel Integration Shielding Code System-Point and Extended Gamma-Ray Sources. |
| PENELOPE2014 | Abstract | C00782 PCX86 01 | Code System for Monte Carlo Simulation of Electron and Photon Transport. |
| PENELOPE-MPI | Abstract | C00713 IBMSP 00 | Code System for Monte Carlo Simulation of Electron and Photon Transport. |
| PENGEOM | Abstract | C00840 MNYCP 00 | Tools for Handling Complex Quadric Geometries in Monte Carlo Simulations of Radiation Transport |
| PEPIN | Abstract | C00285 I0360 00 | Methodology for Computing Concentrations, Activities, Gamma-Ray Spectra, and Residual Heat from Fission Products. |
| PEQAG-2 | Abstract | P00293 IPCAT 00 | A Pre-equilibrium Computer Code With Gamma Emission. |
PERSENT 11.2892
FEDC | Abstract | C00823 MNYCP 02 | Perturbation and Sensitivity Code for Assembly Homogenized Multi-group Transport Problems |
| PF-COMP | Abstract | C00106 C3600 00 | Building Fallout Radiation Protection Factor Analysis. |
| PFPL | Abstract | C00607 D0VAX 00 | Puff-Plume Atmospheric Deposition Model. |
| PGAA-IAEA | Abstract | D00234 MNYCP 00 | Databsae for Prompt Gamma-Ray Neutron Activation Analysis. |
PHAZE
USSO | Abstract | P00432 IBMPC 00 | Parametric Hazard Function Estimation. |
| PHITS-2.88 | Abstract | C00778 MNYCP 05 | Particle and Heavy Ion Transport code System. |
| PHOBIA | Abstract | D00236 PCX86 00 | Photon buildup factors to account for angular incidence on shield walls. |
| PHOEL-2 | Abstract | C00327 I0360 00 | A Monte Carlo Calculation of Initial Energy of Photoelectrons and Compton Electrons Produced by Photons in Water. |
| PHOTX | Abstract | D00136 D0VAX 01 | Photon Interaction Cross Section Library. |
| PHOTX | Abstract | D00136 IBMPC 00 | Photon Interaction Cross Section Library. |
| PICA | Abstract | C00160 D0VAX 00 | Monte Carlo Medium-Energy Photon-Induced Intranuclear Cascade Anal Code System. |
| PICA | Abstract | C00160 I0360 00 | Monte Carlo Medium-Energy Photon-Induced Intranuclear Cascade Anal Code System. |
| PICES | Abstract | P00568 I3033 00 | Probabilistic Investigation of Capacity and Energy Shortages. |
| PICFEE | Abstract | C00175 I3675 00 | Fission Product Inventory Code System. |
| PICTURE | Abstract | P00238 IBMPC 00 | Combinatorial Geometry Printer Plotting. |
| PIEDEC | Abstract | C00566 FM380 00 | A Practical Internal Exposure Dose Evaluation Code. |
| PIGG | Abstract | C00138 C3600 00 | A Multigroup One-Dimensional P-1 Radiation Transport Code System. |
| PIPE | Abstract | C00219 I0360 00 | Numerical Gamma-Ray Transport Code System for Plane/Spherical Geometry. |
| PIXE2010 | Abstract | D00246 MNYCP 00 | Proton/alpha Ionization (K, L, M shell), Tabulated Cross Section Library. |
| PIXSE | Abstract | P00133 I0360 00 | A Generator of Multigroup and Multipoint Cross Sections for Thermal Reactor Calculations. |
| PKI | Abstract | C00573 C0830 00 | A Point Kernel Integration Code For Radiation Shielding of Loop System. |
| PLACID | Abstract | C00381 I0370 00 | Monte Carlo Simulation of Gamma Streaming Through Straight Cylindrical Ducts. |
| PLASMX | Abstract | P00106 C6600 00 | A Multigroup Ionization and Charge Exchange Cross-Section Code System for Neutral Hydrogen Transport in Plasmas. |
| PLOTENDF | Abstract | P00214 I3033 00 | A Program for Producing Graphical Output. |
| PLOTFB | Abstract | P00018 I3675 00 | ENDF/B Data Plotting Code. |
| PLOTNFIT | Abstract | P00382 IBMPC 00 | Code System for Data Plotting and Curve Fitting. |
| PLOT-S | Abstract | P00552 PC586 00 | Plotting Program with Special Features for Windows Environment. |
| PLOTTAB-89.1 | Abstract | P00274 ALLCP 00 | Plot Continuous Curves or Discrete Points. |
| PLUDOS | Abstract | C00313 I0360 00 | Calculator of Ground Level External Gamma-Ray Dose from a Radioactive Plume. |
| PLUMEX | Abstract | C00356 I0360 00 | A Computer Program to Evaluate External Exposures to a Gaussian Plume by Point Kernel Integration. |
| PMK2-VVER440-REPORTS | Abstract | M00012 MNYCP 00 | Results of the Experiments Performed in the PMK-2 Facility for VVER Safety Studies. |
| PN | Abstract | C00818 I0370 00 | MultiGroup Neutron Transport. |
| PNESD | Abstract | D00166 PC386 00 | Proton Nucleus Elastic Scattering Data. |
| POINT2015 | Abstract | D00273 MNYCP 00 | A Temperature-Dependent Linearly Interpolable, Tabulated Cross Section Library Based on ENDF/B |
| POISSX | Abstract | C00819 I0370 00 | Poisson Equation on Rectangle with Various Boundary Conditions. |
| POLLA | Abstract | P00208 I3033 00 | A Fortran Program to Convert R-MATRIX-Type Multilevel Resonance Parameters for Fissile Nuclei into Equivalent KAPUR-PEIERLS-Type Parameters. |
| POLYRES | Abstract | P00438 MNYCP 00 | Richards Equation Solver; Rectangular Finite Volume Flux Updating Solution. |
| POPLIB | Abstract | D00012 I0360 03 | A Compendium of Neutron-Induced Secondary Gamma-Ray Yield and Cross Section Data. |
| POPOP4 | Abstract | P00011 I3675 00 | Converter of Gamma-Ray Spectra to Secondary Gamma-Ray Production Cross Sections. |
| POWER | Abstract | P00069 C7600 00 | Source Distribution Input Data Generator for ANISN Code. |
| PREANG | Abstract | P00166 C0175 00 | Calculation of Pre-equilibrium Angular Distributions with the Exciton Model. |
| PRE-ANISN | Abstract | P00332 PC386 00 | A Preprocessing Code for ANISN and Other Radiation Transport Codes. |
| PRECO2006 | Abstract | P00226 MNYCP 02 | Exciton Model Code System for Calculating Preequilibrium and Direct Double Differential Cross Sections. |
| PR-EDB | Abstract | D00196 IBMPC 03 | Power Reactor Embrittlement Data Base. |
| PREDEX-1 | Abstract | P00597 I0370 00 | U, Pu, Nitric Acid Distribution in Counter Current Solvent Extraction. |
| PREM | Abstract | P00224 I0360 00 | Code System for Pre-equilibrium Process with Multiple Nucleon Emission. |
| PREMOR | Abstract | C00369 I0360 00 | A Point Reactor Exposure Code System for Survey Nuclear Analysis of Power Plant Performance. |
| PREP/SPOP | Abstract | C00772 MNYCP 00 | Uncertainty and Sensitivity Analysis Monte Carlo Program and Input Preparation. |
| PREPRO2019 | Abstract | P00351 MNYCP 10 | Pre-Processing Code System for Data in ENDF/B Format. |
| PREST | Abstract | C00355 I0360 00 | Calculator of Pressure and Temperature Transient in Containment Studies. |
| PRESTO | Abstract | C00549 D8810 00 | Point Kernel Calculation for Complex and Time-Dependent Gamma-Ray Source Spectra. |
| PRESTO-II | Abstract | C00504 I0360 00 | Code System for Low-Level Waste Environmental Transport and Risk Assessment. |
| PRIMEDANA-2 | Abstract | C00490 I3081 00 | Collapses Multigroup Cross Sections and Obtains Reaction Parameters by Solving Transport or Diffusion Equations. |
| PRISIM | Abstract | C00574 IBMPC 00 | Plant Risk Status Information Management System. |
| PROB | Abstract | C00287 I0370 00 | Multigroup One-Dimensional Transport Code System, Collision Probability Method. |
| PROCIV | Abstract | C00488 U1110 00 | A Code System for Calculating the Protection Factors Against Radioactive Fallout for Apartment Buildings. |
| PSAPACK-4.2 | Abstract | P00613 PCX86 00 | Probabilistic Safety Analysis with Fault Event Trees. |
| PSDREC | Abstract | P00441 DP011 00 | Code System for Power Spectral Density Recognition Continuous On-line Reactor Surveillance. |
| 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. |
| PUCOR | Abstract | D00067 I3691 00 | 84 Group Neutron Cross Sections for Uranium-Plutonium Cycle LWR and PWR Models in AMPX Master Library Format. |
| PUDK | Abstract | D00074 I0360 00 | Measured Results of Delayed Beta- and Gamma-Ray Spectra Due to Thermal-Neutron Fission of Pu239 and Pu241. |
| PUFF-IV | Abstract | P00534 MNYCP 01 | Determination of Multigroup Covariance Matrices from ENDF/B-V Uncertainty Files. |
| PURSE | Abstract | C00338 C6600 00 | A Plutonium Radiation Source Code System. |
| PUSHLD | Abstract | C00271 C0074 00 | Gamma-Ray Three-Dimensional Calculation of Dose Rates from Plutonium in Various Geometries. |
| PUTZ 2.1 | Abstract | C00595 IBMPC 00 | A Point-Kernel Photon Shielding Code. |
| PVC | Abstract | D00048 I3691 00 | 36 Group, P5, Photon Interaction Cross Sections for 38 Materials in ANISN Format. |
| PVE | Abstract | D00126 I3033 00 | 38 Group, P8, Photon Interaction Cross Sections in ANISN Format from VITAMIN-E. |
| PVIS-4 | Abstract | C00798 MNYCP 00 | Pressure Vessel Irradiation Source. |
| PWR-AXBUPRO-GKN | Abstract | D00209 MNYCP 00 | Measured Axial Burnup Profiles for NeckarWesthiem PWR Reactors. |
| PWR-AXBUPRO-SNL | Abstract | D00201 MNYCP 00 | Axial Burnup Profile Database for Pressurized Water Reactors. |