Computer Programs

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nea-1732 | 3D-TRANS-2003, Workshop on Common Tools and Interfaces for Radiation Transport Codes |

ests0171 | ADASAGE, ADA Application Development System |

ests0165 | AES, Automated Construction Cost Estimation System |

iaea1251 | AMICO, Cross-Sections Data for ANISN, DOT from WIMS Library |

ccc-0519 | AUS, Neutron Transport and Gamma Transport System for Fission Reactors and Fusion Reactors |

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 |

psr-0117 | BINX, MINX Utility and SPHINX Utility, BCD to BIN Library Conversion |

nea-0438 | BRIGITTE-KA, ENDF/B to KEDAK Data Conversion with Resonance Cross-Sections Tables Generator |

nea-0866 | BTPLOT BTSPEC EXSPEC ORDTAB TABLST, Retrieval of ENDF/B Decay Spectra |

nesc9789 | CDMS, Cost Data Management System Spread Sheet |

uscd1208 | CHECKR, ENDF/B Format Check |

psr-0117 | CINX, MINX Utility and SPHINX Utility, Library Data Collapsing |

nea-0915 | COGEND, Decay Data Generated in ENDF-6 Format |

psr-0607 | COGLIBMAKER2014, Data Conversion Utility |

nea-0325 | CONDENSE, Conversion of JAERI Fast-Set to ABBN Format with Self-Shielding |

iaea1307 | CONVERT2010, FORTRAN Program Converter for Different Computers |

nea-0948 | CRECT-J, Input Preparation of Evaluated Data in ENDF-4, ENDF-5 and ENDF-6 Formats |

iaea1308 | DICTIN2010, Reaction Index Generated for ENDF Format |

uscd1237 | DRAGON2PARTISN, Cross-Sections Data Generation for PARTISN4.0 |

uscd1235 | ENDF-UTILITY-CODES, codes to check and standardize data in the Evaluated Nuclear Data File (ENDF) |

uscd1149 | ENSDF ADDGAM, Adds Gammas to Adopted Data Sets |

uscd1149 | ENSDF ALPHAD, Calculation Alpha Hindrance Factors |

uscd1149 | ENSDF AVETOOLS, Three statistical methods to calculate averages of experimental data with uncertainties |

uscd1149 | ENSDF BRICC, Interpolates Band-Raman internal conversion and electron-positron pair coefficients and E0 form factors |

uscd1149 | ENSDF DELTA, Gamma-Gamma Correlation Analysis |

uscd1149 | ENSDF ENSDAT, Graphics and Tables Generation from ENSDF Data |

uscd1149 | ENSDF FETCH, Indexing of ENSDF Files |

uscd1149 | ENSDF FMTCHK, Format Checking Program |

uscd1149 | ENSDF GABS, Absolute Gamma-Ray Intensities from ENSDF Data |

uscd1149 | ENSDF GTOL, Least Squres Fit of Gamma Spectra and Level Assignment |

uscd1149 | ENSDF HSICC, Interpolation Between Hager-Seltzer and Dragoun-Plajner-Schmutzler |

uscd1149 | ENSDF LOGFT, Beta-Decay log-ft and Partial Capture Calculation |

uscd1149 | ENSDF MEDLIST, Dose Rates from Nuclear Decay Data (X-ray intensities) |

uscd1149 | ENSDF NSDFLIB, Subroutine Library for ENSDF Programs |

uscd1149 | ENSDF PANDORA, Physics Checks on ENSDF Data |

uscd1149 | ENSDF PROCESSING CODES, Analysis and Utility Programs |

uscd1149 | ENSDF RADLST, Dose Rates from Nuclear Decay Data (decay of nuclei) |

uscd1149 | ENSDF RULER, Reduced Transition Problems Abilities Calculation |

uscd1149 | ENSDF SPINOZA, Tables of Levels, Decay, Gammy-Ray Data from ENSDF |

uscd1149 | ENSDF TREND, Tabulation of ENSDF Data |

iaea1285 | EPICSHOW, Interactive Viewing of EPIC (Electron Photon Interaction Code) Data Library |

nea-1048 | ETOBOX, Cross-Sections Library Generated from ENDF/B for Program BOXER |

nesc0350 | ETOE ETOE-2, Cross-Sections Library for Program MC**2 Generator from ENDF/B |

nea-0630 | ETOI, Format Conversion of Resonance Parameter from ENDF/B to Program IRESINT-3 Library |

iaea0898 | F5TAB, ENDF/B-4 FILE 5 Data Conversion to Tabulated Form |

iaea1245 | FDMXPC, ENDF/B Processing, with Reich-Moore and Adler-Adler Resonance Parameter Calculation |

iaea1309 | FIXUP2010, ENDF Format Redundant Cross-Sections Check |

uscd1209 | FIZCON, ENDF/B Cross-Sections Redundancy Check |

nesc9915 | FRAMIS, Relational Data Base Management System |

nea-1459 | GALIST, Decay Gamma Spectra Retrieval from ENSDF |

nea-1175 | GAMFIL, Photon Production Cross-Sections in ENDF/B Format |

uscd1210 | GETMAT, ENDF/B Material Retrieval |

psr-0229 | GIP, Group Organized Cross-Sections Library for ANISN, DOT |

psr-0192 | GLUCS, Experimental Reaction Cross-Sections Evaluation for ENDF/B-5 |

uscd1211 | GRALIB, DISSPLA Plot Routines Emulator |

nea-1111 | GROUPXS, MF6 Format ENDFB-6 Continuum Region Diffusion Cross-Sections Processing |

iaea1253 | HOMO, Homogenization of ANISN and DOT Condensed Cross-Sections Output |

iaea1248 | INDXENDF, Preparation of Visual Catalogue of ENDF Format Data |

uscd1212 | INTER, ENDF/B Thermal Cross-Sections, Resonance Integrals, G-Factors Calculation |

uscd1213 | INTLIB-6, Graphic Device Interface Library for ENDF/B Processing Codes |

nea-0317 | JFUSER, JAERI Fast-Set Group Constant Collapsing and Data Conversion for Program LTFR-70 |

nea-0578 | KEMA, KEDAK Utility, Data Update |

nea-0342 | KTOE, KEDAK to ENDF/B Format Conversion with Linear Linear Interpolation |

nesc0691 | LASIP-3, CCCC Utility for BCD to BIN Conversion and BIN Data Listing |

iaea1310 | LEGEND2010, Angular Distribution Table Calculations in ENDF Format |

iaea1311 | LINEAR2010, Linear-Linear Interpolation of ENDF Format Cross-Sections |

psr-0117 | LINX, MINX Library Utility, Data Merge |

uscd1214 | LISTEF, ENDF/B Data File Summary List |

nea-0316 | LTFR-4, Library Generated for Fast Reactor Design Program from JAERI Fast-Set MultiGroup Constant |

nea-0517 | MAPLIB, Thermodynamics Materials Property Generator for FORTRAN Program |

psr-0117 | MARS-ORNL, Processing Program Collection for AMPX, CCCC, ANISN, DOT, MORSE Format Library |

nea-0452 | MCDATA, MC**2 Cross-Sections Conversion for Programs CITATION, ANISN, DOT |

iaea1312 | MERGER2010, Merges ENDF/B Data by Material Number or Identifier |

nea-0474 | MISSIONARY, ENDF/B to UKNDL Format Conversion |

iaea1313 | MIXER2010, Cross Sections Calculations for a Composite Mixture of ENDF Format Material |

psr-0365 | MOCUP, MCNP/ORIGEN Coupling Utility Programs |

nea-1347 | NSLINK, Coupling of NJOY Cross-Sections Generator Code to SCALE-3 System |

nea-1492 | NUCLEUS-CHART, Interactive Chart of Nuclides |

nea-1271 | OMICRON, LLNL ENDL Charged Particle Data Library Processing |

uscd1205 | PCNUDAT-PCNULIB, Nuclear Properties Data Base and Retrieval System |

iaea0936 | PLOTC4, Plotting of ENDF/B and EXFOR Data |

uscd1215 | PLOTEF, ENDF/B Data Plot |

nea-0522 | PLOTENDF, Log-Log Plot of ENDF/B Point Cross-Sections |

iaea0944 | POLLA/IECTA, ENDF/B Reich-Moore to Adler-Adler Resonance Parameter Conversion |

iaea1379 | PREPRO2010, Data Preparation and Management, Subsidiary Calculations (ENDF Format) |

nesc0846 | PROMSYS, Plant Equipment Maintenance and Inspection Scheduling |

nea-1138 | PSACON, Conversion Program for PSAOUT-I Output Files |

uscd1216 | PSYCHE, ENDF/B Data Consistency Check in ENDF Format |

nea-0914 | REFIT, Multilevel Resonance Parameter Least Square Fit of Neutron Transmission, Capture, Fission & Self Indication Data |

iaea1314 | RELABEL2010, Labels FORTRAN Statements in ENDF Format Processing Programs |

ests0579 | REMIT, Radiation Exposure Monitoring and Information Transmittal System |

psr-0482 | REMIT5.1, Radiation exposure monitoring and information transmittal system |

nea-1405 | SCALPLO, Plotting of Flux Output from SCALE Program |

psr-0352 | SCAMPI, Problem Dependent Library Preprocessing in AMPX Format |

uscd1217 | SETMDC: Preprocessor for CHECKR, FIZCON, INTER, etc. ENDF Utility source codes |

iaea1356 | SGNUCDAT, Nuclear Data Display for IAEA Safeguard Material Analysis |

iaea1283 | SIXPAK2010, ENDF Format Double Differential Cross Section Converter to Single Differential Format |

nesc9770 | SLIB77, Source Library Data Compression and File Maintenance System |

psr-0174 | SORA, Radionuclide Analysis Data Storage and Retrieval |

iaea1433 | SPECTRA2010, Convert model and general tabulation to linearized spectra (MF=5) |

uscd1218 | STANEF, ENDF/B Book-keeping Operations for ENDF Format Files |

nea-0634 | THERLIB, Library Generated for THERMOS from FACEL Library |

nea-0634 | THERMLIB, Generator and Edit of Program THERMOS-OTA Library |

nea-1406 | TOPICS-B, Neutron and Gamma Cross-Sections Library Handling in FIDO Format |

psr-0317 | TRANSX-2.15, Neutron Gamma Particle Transport Tables from MATXS Format Cross-Sections |

psr-0015 | UKE, Format Conversion from UKNDL to ENDF/B |

nea-1139 | UNC32/33, Covariance Matrices from ENDF/B-5 Resonance Parameter Uncertainties |

nea-0356 | UTOE, UKNDL to ENDF/B Format Conversion with Log-Log Interpolation and Angular Distribution Tables |

iaea0932 | VIRGIN2010, Calculates Uncollided Neutron Flux and Neutron Reactions from Transmission in ENDF Format |

iaea1210 | WEDRO, Data Processing Routines for WIMS-D/4 WIMSE File |

iaea1243 | WILIT, Utility Program for WIMS Library Handling |

iaea0946 | WILMA, WIMS Nuclear Data Library Maintenance |

iaea1254 | WINTER, Interactive WIMS Input Preparation |

iaea0897 | X4ECS, ENDF/B-4 and EXFOR Data Comparison |

iaea0896 | X4R, EXFOR Evaluated Data Retrieval |

iaea0936 | X4TOC4, Neutron Cross-Sections Data Conversion from EXFOR to Computation Format |