Online Catalog
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Click on RSICC Tapelist to view list of files distributed with package.

Note: RESTRICTIONS APPLY TO SOME PACKAGES -
810 -- US DOE 10CFR810 Jurisdiction
FEDC -- US Government Agencies and Their Contractors Only
OECD -- Restricted/See Abstract
USSO -- US Distribution Only
USUNV -- US Universities Only
Packages starting with B
Package NameAbstractRSICC TapelistTitle
BABELAbstractD00104 I3033 00Multi-Purpose Neutron and Gamma-Ray Cross Section Library for Fast Reactor Shielding Design.
BALTOROAbstractC00479 C6600 00Code for Coupling of Monte Carlo and Discrete Ordinates Radiation Transport Calculations.
BARC-35AbstractD00124 IBMMF 0035-Group Neutron Cross Sections and Resonance Self-Shielding Factors Generated in ISOTXS and BRKOXS Format from ENDF/B-IV Using MINX.
BASACFAbstractP00285 IBMPC 00Bayesian Approach to Spectrum Adjustment with Covariance Filter.
BAYESAbstractP00205 DP010 00User's Guide for A General-Purpose Computer Code System for Fitting a Functional Form to Experimental Data.
BCGAbstractC00578 C0170 00A Code For Calculating Pointwise Neutron Spectra and Criticality in Fast Reactor Cells.
BEACON MOD3AbstractP00402 CDCMF 00Code System for Thermal-Hydraulic Analysis of Nuclear Reactor Containments.
BEBCAbstractC00077 I7090 00Electron Bremsstrahlung Penetration Code for Space Vehicles.
BEDAbstractC00078 I7090 00Electron Penetration Code for Space Vehicles.
BERMUDAAbstractC00616 FV260 03Discrete Ordinates Code System for Shielding Analysis for Use with Fusion and Fission Reactors.
BEST-5AbstractP00591 I0370 00Power Reactor Fuel Cycle Optimization by Bellman Method.
BETA IIAbstractC00117 C6600 00Monte Carlo Bremsstrahlung and Electron Transport Analysis in Geometry.
BETA IIAbstractC00117 I0360 00Monte Carlo Bremsstrahlung and Electron Transport Analysis in Geometry.
BETA-S 6AbstractC00657 MNYCP 01Code System to Calculate Multigroup Beta-Ray Spectra.
BFR
USSO
AbstractP00449 C0176 00Code System for Common Cause Failure Data Analysis.
BIGGIAbstractC00066 I3675 00Numerical Gamma-Ray Transport Code for Plane or Spherical Multilayer Geometry, Versions 3P &4T.
BIGGIAbstractC00066 U1108 00Numerical Gamma-Ray Transport Code for Plane or Spherical Multilayer Geometry, Versions 3P and 4T.
BIGGI-4TAbstractC00780 I0360 00Gamma Transport in Multi-Region Shield in Planar or Spherical Geometry.
BISON 1.5AbstractC00464 HM200 00A One-dimensional Discrete Ordinate Transport and Burnup Calculation Code. (Burnup of Isotopes and One-Dimensional Transport).
BISON-CAbstractC00659 MNYWS 00One-Dimensional Discrete Ordinate Transport and Burnup Calculation Code System.
BLOCKAGE V2.5RAbstractP00377 IBMPC 00Code System to Calculate Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in a BWR.
BLT-FEMWATER
USSO
AbstractC00633 PC386 00Code System to Solve for Release and Transport of Contaminants through Saturated/Unsaturated Media.
BMC-MGAbstractC00291 C6600 00Multigroup Monte Carlo Neutron and Gamma-Ray Shielding Code System for Plutonium.
BOB-7 SERIESAbstractP00084 F2306 00Theory and Use of Gamma-Ray Spectrum Analysis Codes for Ge(Li) Detectors.
BOLD VENTURE IVAbstractC00459 I3033 00A Reactor Analysis Code System.
BONAbstractP00173 I0360 00A Code System for Unfolding Multisphere Spectrometer Neutron Measurements.
BOREHOLE-EB6.8-MGAbstractD00268 MNYCP 00Multi-Group Cross-Section Library for Deterministic and Monte Carlo Codes.
BOT3P-5.3AbstractP00530 MNYCP 02Code System for 2D and 3D Mesh Generation and Graphical Display of Geometry and Results for Radiation Transport Codes.
BOXERAbstractC00766 MNYWS 00Fine-flux Cross Section Condensation, 2D Few Group Diffusion and Transport Burnup Calculations
BPAbstractD00008 I0360 00Data for Selected Shielding Benchmark Problems Specified in ORNL-RSIC-25, Shielding Benchmark Problems.
BPPCAbstractC00076 I7090 00Proton Penetration Codes for Space Vehicles.
BREESE-IIAbstractP00143 I3033 00Auxiliary Routines for Implementing the Albedo Option in the MORSE Monte Carlo Code System.
BREMRADAbstractC00031 I7090 00External and Internal Bremsstrahlung Calculation Code.
BRHGAMAbstractC00350 I3033 00Monte Carlo Estimation of Absorbed Dose from X-Ray Sources in Phantom Man.
BRMSTKAbstractP00044 C6600 00CSEWG Integral Data Testing Shielding Experiment Code System.
BRMSTKAbstractP00044 I3691 00CSEWG Integral Data Testing Shielding Experiment Code System.
BSPRP2AbstractP00372 IRISC 00Code System to Process DORT Boundary-Flux Files.
BUCORSTAbstractP00339 PC386 00A Code to Prepare Burnup-Dependent Multigroup Nuclear Reactor Source Terms.
BUGENDF70.BOLIBAbstractD00262 PCX86 00ENDF/B-VII.0 Broad-Group Coupled Cross Section Library for LWR Shielding & Pressure Vessel Dosimetry Applications.
BUGJEFF311.BOLIBAbstractD00254 MNYCP 01JEFF-3.1.1 Broad-Group Coupled Cross Section Library For LWR Shielding & Pressure Vessel Dosimetry Applications.
BUGLE-80AbstractD00075 IBMPC 02Coupled 47 Neutron, 20 Gamma-Ray Group, P3, Cross Section Library for LWR Shielding Calculations by the ANS-6.1.2 Working Group on Multigroup Cross Sections. We recommend ENDF/B-VI derived data in DLC-185/BUGLE-96.
BUGLE-80AbstractD00075 IBMPC 03Coupled 47 Neutron, 20 Gamma-Ray Group, P3, Cross Section Library for LWR Shielding Calculations by the ANS-6.1.2 Working Group on Multigroup Cross Sections. We recommend ENDF/B-VI derived data in DLC-185/BUGLE-96.
BUGLE-80AbstractD00075 PC386 01Coupled 47 Neutron, 20 Gamma-Ray Group, P3, Cross Section Library for LWR Shielding Calculations by the ANS-6.1.2 Working Group on Multigroup Cross Sections. We recommend ENDF/B-VI derived data in DLC-185/BUGLE-96.
BUGLE-96AbstractD00185 ALLCP 00Coupled 47 Neutron, 20 Gamma-Ray Group Cross Section Library Derived from ENDF/B-VI for LWR Shielding and Pressure Vessel Dosimetry Applications.
BULK_C-12AbstractC00738 PC586 00Code System to Estimate Neutron and Photon Effective Dose Rates from Medium Energy Protons or Carbon Ions Through Concrete or Concrete/Iron.
BULK-IAbstractP00574 PCX86 00Radiation Shielding Tool for Proton Accelerator Facilities.
BURDAbstractP00582 IBMPC 00Bayesian Estimation in Data Analysis of Probabilistic Safety Assessment.
BURP-2AbstractC00237 C6600 00Calculation of Buildup and Decay of Radioactive Fission Products.
BUSHAbstractC00333 I0360 00A Code to Calculate Radiation Doses Inside Buildings from Routine Releases of Radionuclides to the Atmosphere.
BUTTERCUPAbstractC00779 MNYCP 00A Dual-Layer Photon Buildup Factor Code.
BWR-LTASAbstractC00485 I3033 01Code System for Boiling Water Reactor Long-Term Accident Simulation.
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.