Online Catalog
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Note: RESTRICTIONS APPLY TO SOME PACKAGES -
810 -- US DOE 10CFR810 Jurisdiction
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Packages with Keyword: DETECTOR RESPONSE
Package NameAbstractRSICC TapelistTitle
BUGLE-93AbstractD00175 ALLCP 01Coupled Neutron, Gamma-Ray Group Cross Section Library Derived from ENDF/B-VI for LWR Shielding and Pressure Vessel Dosimetry Applications.
BUGLE-96AbstractD00185 ALLCP 00Coupled Neutron, Gamma-Ray Group Cross Section Library Derived from ENDF/B-VI for LWR Shielding and Pressure Vessel Dosimetry Applications.
CEAR-PPUAbstractP00528 PC586 00Code System for Monte Carlo Simulation of Detector Pulse Pile Up.
DABL69AbstractD00130 I0360 01Defense Nuclear Applications Broad-Group Library based on ENDF/B-V in ANISN Format.
DENISAbstractP00082 I0360 00Monte Carlo Simulation of the Capture and Detection of Neutrons with Large Liquid Scintillators.
DETAN 95AbstractP00361 MNYCP 00Code System to Calculate Spectrum-Averaged Cross Sections and Detector Responses in Neutron Spectra.
ELANAbstractP00141 ICL00 00Neutron Cross-Section Self-Shielding Code System.
GAINCALBAbstractP00056 I0360 00Determination of the Gain Used with Organic Scintillation Detect.
GAMMAAbstractP00095 I0360 00Monte Carlo Code System for Calculating Efficiencies and Response Functions of NaI(Tl) Crystals for Gamma Rays from Thick Disk Sources.
GAMX1AbstractP00209 I0370 00A Computer Code System for Evaluating Spectra Peak Areas.
LOGNORMLAbstractP00307 IPCAT 00Lognormal Probability Analysis Code System for Estimating Doses in Epidemiologic Studies.
MARTHAAbstractP00232 I0360 00Monte Carlo Response Function Calculation for Sodium Iodide Photon Detectors.
MICAPAbstractP00261 I3033 00A Monte Carlo Code System for Analysis of Ionization Chamber Responses.
MORNAbstractP00062 I0360 00Calculation of the Response of Sodium Iodide Crystals to Gamma Rays.
O5SAbstractP00014 DP010 00Response Function Generator--An O5R Monte Carlo Code for Calculating Pulse Height Distributions Due to Monoenergetic Neutrons Incident on Organic Scintillators.
O5SAbstractP00014 I3675 00Response Function Generator--An O5R Monte Carlo Code for Calculating Pulse Height Distributions Due to Monoenergetic Neutrons Incident on Organic Scintillators.
REFERDOUAbstractP00249 FM380 00Code System for NE-213 Unfolding of Neutron Spectra up to 100 MeV with Response Function Error Propagation.
REFUM-BROADAbstractP00039 F2307 00Monte Carlo Codes for Calculating Efficiencies and Response Functions of NaI(Tl) Crystals for Thick Disk Gamma-Ray Sources.
REPCAbstractP00195 C0000 00Estimation of Nuclear Reaction Effects in Proton-Tissue-Dose Calculations.
RESPMGAbstractP00060 I0360 00Response Matrix Generation Code System.
SCINFULAbstractP00267 CY0MP 00Scintillator Full Response to Neutron Detection.
SCINFULAbstractP00267 D8600 00Scintillator Full Response to Neutron Detection.
SINBAD 2017.12AbstractD00237 MNYCP 05Shielding Integral Benchmark Archive and Database.
SINBAD SEARCH TOOLAbstractP00580 MNYCP 00SINBAD Search Tool
SPEC-4AbstractP00099 I0360 00Calculated Recoil Proton Energy Distributions from Monoenergetic and Continuous Spectrum Neutrons.
VELMAbstractD00133 I0360 00Multigroup Cross-Section Libraries Based on ENDF/B-V Data for Sodium-Cooled Reactor Shield Analysis.
VITAMIN-B7/BUGLE-B7AbstractD00245 MNYCP 01Broad-Group and Fine-Group and Coupled Neutron/Gamma Cross-Section Libraries Derived from ENDF/B-VII.0 Nuclear Data.
WINDOWS IIAbstractP00161 I0370 00A Program for the Analysis of Spectral Data Foil Activation Measurements.
The Radiation Safety Information Computational Center (RSICC) is a Department of Energy Specialized Information Analysis Center (SIAC) authorized to collect, analyze, maintain, and distribute computer software and data sets in the areas of radiation transport and safety. RSICC resides in the Reactor and Nuclear Systems Division (RNSD) at Oak Ridge National Laboratory.