Online Catalog
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Packages with Keyword: RADIATION ENVIRONMENT
Package NameAbstractRSICC TapelistTitle
AIRDIFAbstractC00360 C6600 00A Two-Dimensional Atmospheric Radiation Diffusion Code.
AIRFEWGAbstractD00049 I0360 00Results of ANISN Multigroup Calculations of Gamma-Ray, Neutron, and Secondary Gamma-Ray Transport in Infinite Homogeneous Air Using DLC-31/(DPL-1/FEWG1) Cross Sections.
ARCAbstractC00224 C6600 00Aircraft Radiation Transport Code System, Crew Dose Calculation.
CDRAbstractC00182 C6600 00A Constant Dose Range Code System, Using the LANL-NWEF Neutron-Gamma-Ray Air Flux Tape.
CDRAbstractC00182 I0360 00A Constant Dose Range Code System, Using the LANL-NWEF Neutron-Gamma-Ray Air Flux Tape.
COMRADEX4AbstractC00332 I0360 00Evaluator of Potential Radiological Doses in the Near (< 10 km) Environment of Radioactive Release.
DIFMODAbstractC00572 I3083 00A Computer Program To Calculate The Leaching of Radionuclides and the Corrosion of Cemented Waste Forms in Water or Brine.
DOSDAT II-81AbstractD00079 I0370 00Dose-Rate Conversion Factors for External Exposure to Photons and Electrons.
DOSDAT-DOEAbstractD00144 ALLMF 00Dose-Rate Conversion Factors for External Exposure to Photons and Electrons.
DOSDAT-DOEAbstractD00144 IBMPC 01Dose-Rate Conversion Factors for External Exposure to Photons and Electrons.
DUST-BNLAbstractC00634 PC386 00Disposal Unit Source Term by One-Dimensional, Transient, Finite-Difference, Subsurface Release and Transport of Contaminants.
FGR-DOSEAbstractD00167 ALLCP 01Dose Coefficients from Federal Guidance Reports 11 and 12.
FTFAbstractD00056 I0360 00Multigroup Neutron and Gamma-Ray Dose Transmission Factors for Concrete Slabs.
HALLMARKAbstractD00005 I0360 00Discrete Ordinates and Monte Carlo Results of Neutron and Secondary Gamma-Ray Transport in Air-Over-Ground Geometry.
IRDF82AbstractD00094 I0360 00The International Reactor Dosimetry File.
LADTAP IIAbstractC00363 C7600 00Code System for Calculating Radiation Exposure to Man from Routine Release of Nuclear Reactor Liquid Effluents.
LADTAP IIAbstractC00363 D0780 00Code System for Calculating Radiation Exposure to Man from Routine Release of Nuclear Reactor Liquid Effluents.
LADTAP IIAbstractC00363 I3033 00Code System for Calculating Radiation Exposure to Man from Routine Release of Nuclear Reactor Liquid Effluents.
MODELAbstractC00329 I3033 00Models of Trapped Proton and Electron Environments for Solar Maximum and Minimum.
NRCDOSE 2.3.20AbstractC00684 PC586 14Code System for Evaluating Routine Radioactive Effluents from Nuclear Power Plants with a Windows Interface.
NRCDOSE72V1.2.3AbstractC00768 PCX86 03Code System for Evaluating Routine Radioactive Effluents from Nuclear Power Plants with a Windows Interface.
PREP/SPOPAbstractC00772 MNYCP 00Uncertainty and Sensitivity Analysis Monte Carlo Program and Input Preparation.
REPRISK PC 1.02AbstractC00586 PC386 01Repository Risk Assessment Software for Personal Computers.
SHARDAAbstractC00521 C0740 00Sample Heat, Activity, Reactivity, and Dose Analysis for Safety Analysis of Irradiations in a Research Reactor.
SOFIPAbstractC00358 I3033 00Evaluator of Space Radiation Environment Encountered by Geocentric Satellites.
TRECOAbstractC00116 I3675 00An Orbital Integration Estimation of Trapped Radiation.
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.