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Click on Abstract to read the package abstract.
Click on RSICC Tapelist to view list of files distributed with package.
Note: RESTRICTIONS APPLY TO SOME PACKAGES -
810 -- US DOE 10CFR810 Jurisdiction
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| Packages starting with N |
| Package Name | Abstract | RSICC Tapelist | Title |
| NAAPRO | Abstract | C00722 PC586 00 | Neutron Activation Analysis PRognosis and Optimization Code System. |
| NAB | Abstract | D00018 I0360 00 | 100-Group, P3, Neutron Cross Section Data for Sodium and Aluminum. |
| 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. |
| NACT | Abstract | C00502 U1100 00 | Screening Program for Neutron Activation Products. |
| NAISAP | Abstract | P00085 F2306 00 | Theory and Use of Gamma-Ray Spectrum Analysis Codes for NaI(Tl) Detectors. |
| NANICK | Abstract | P00120 I0360 00 | Infinitely-Diluted Multigroup Cross-Section Generator - from ENDF/B. |
| NAP | Abstract | C00101 I7090 00 | Multigroup Time-Dependent Neutron Activation Prediction Code. |
| NASIF-NARES | Abstract | P00121 I0360 00 | A Code System for Computing Shielding Factors from ENDF/B Tapes. |
| NAUA-MOD5 NAUA-MOD5/M | Abstract | P00556 MNYCP 00 | Aerosols in Reactor Containment During Meltdown. |
| NCRP49 | Abstract | C00462 IBMPC 00 | X-Ray Shield Calculation System. |
| NCSP-DAT | Abstract | M00002 MNYCP 01 | Nuclear Data in Support of the Nuclear Criticality Safety Program. |
| NEACRP-H2O-LATTICES | Abstract | D00265 MNYCP 00 | Compilation of Reactor Physics Measurements in LWRs Lattices. |
| NESTLE 5.2.1 | Abstract | C00641 MNYCP 04 | Code System to Solve the Few-Group Neutron Diffusion Equation Utilizing the Nodal Expansion Method (NEM) for Eigenvalue, Adjoint, and Fixed-Source |
| NEUPAC | Abstract | P00177 FM200 00 | Neutron Unfolding Code System for Calculating Neutron Flux Spectra from Activation Data of Dosimeter Foils. |
| NEVEMOR | Abstract | P00026 I3675 00 | Multigroup-Multiregion Calculation of Flux Spectra and Energy Deposition for Fast Neutrons. |
| NITRAN | Abstract | C00582 FM380 00 | Neutron Transport Code System Based On Anisotropic Scattering. |
| NJOY91.119 | Abstract | P00171 MFMWS 04 | Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data. |
| NJOY94.61 | Abstract | P00355 MFMWS 03 | Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data. |
| 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. |
| NJOY-UTIL-EIR | Abstract | P00296 C0825 00 | Utilities For the NJOY (6/83) Nuclear Data Processing System. |
| NMTC/JAERI97 | Abstract | C00694 SUN05 00 | Monte Carlo Nucleon Meson Transport Code System. |
| NMTC/JAM | Abstract | C00717 PC586 00 | High Energy Particle Transport Code System. |
| NONSAP-C | Abstract | P00458 C7600 00 | Code System for Analysis of 3-D Reinforced Concrete Structures. |
| NORMA | Abstract | P00471 PC586 00 | Code System to Solve Burnup Dependent Neutron Diffusion Equations in Two and Three Dimensions. |
| NORMA-FP | Abstract | P00470 PC586 00 | Code System to Perform Neutronic and Thermal-Hydraulic Subchannel Analysis from Converged Coarse-Mesh Nodal Solutions. |
| NOX | Abstract | D00017 I0360 00 | 199-Group, P5, Coupled Neutron and Secondary Gamma-Ray Cross Section Data for Nitrogen and Oxygen. |
| NPCSL-81 | Abstract | D00082 I0370 00 | Point Neutron Cross Sections Generated from ENDF/B-IV with the NPTXS Modules of PSR-63/AMPX-II. |
| NPTXS | Abstract | P00090 I0360 00 | Data Generator: Neutron Point Cross Sections from ENDF/B Resolved and Unresolved Resonance Parameters. |
| NRCDOSE 2.3.20 | Abstract | C00684 PC586 14 | Code System for Evaluating Routine Radioactive Effluents from Nuclear Power Plants with a Windows Interface. |
| NRCDOSE72V1.2.3 | Abstract | C00768 PCX86 03 | Code System for Evaluating Routine Radioactive Effluents from Nuclear Power Plants with a Windows Interface. |
| NRCPAGE | Abstract | P00491 DVX11 00 | Code System to Detect Recurring Loss of Special Nuclear Materials. |
| NRCPIPES 2.0A | Abstract | P00429 IBMPC 00 | Code System for Fracture Mechanics Analysis of Circumferential Surface Cracks in Pipes. |
| NRN | Abstract | C00054 C6600 00 | Multigroup Removal-Diffusion Code System for Planes, Cylinders and Spheres. |
| NSLINK | Abstract | P00314 D0VAX 00 | NJOY SCALE LINK. |
| NUCCON | Abstract | C00439 S7800 00 | A Code System for Calculation of Time-Dependent Nuclide Concentrations, Activity, Gamma-Ray Dose Rate and Biological Hazard Potential of Fusion Reactor Materials Due to Neutron Irradiation. |
| 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. |
| NUCHART | Abstract | P00545 IBMPC 00 | Nuclear Properties and Decay Data Chart of Nuclides. |
| NUCWIZ | Abstract | P00616 PCX86 00 | NucWiz |
| NUFACE | Abstract | P00284 CYXMP 00 | An Interface Code For The Calculation of Nuclear Responses. |
| NUGAM 2&3 SSLAB | Abstract | C00210 I0360 00 | Monte Carlo Prediction of Photon Transport Distributions. |
| NUTRAN | Abstract | C00675 I0370 00 | Code System for Long-Term Repository Safety Analysis. |
| NX1-NX2 | Abstract | P00310 D0VAX 00 | Code System to Calculate Excitation Functions for (n,charged particle) Reactions. |