RSICC Catalog

Online Catalog

Click on Package Name to get detailed information.
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
FEDC -- US Government Agencies and Their Contractors Only
OECD -- Restricted/See Abstract
RUGA -- Restricted Use Government Authorized
USSO -- US Distribution Only
USUNV -- US Universities Only

Packages starting with B
Package Name	Abstract	RSICC Tapelist	Title
BABEL	Abstract	D00104 I3033 00	Multi-Purpose Neutron and Gamma-Ray Cross Section Library for Fast Reactor Shielding Design.
BALTORO	Abstract	C00479 C6600 00	Code for Coupling of Monte Carlo and Discrete Ordinates Radiation Transport Calculations.
BARC-35	Abstract	D00124 IBMMF 00	35-Group Neutron Cross Sections and Resonance Self-Shielding Factors Generated in ISOTXS and BRKOXS Format from ENDF/B-IV Using MINX.
BASACF	Abstract	P00285 IBMPC 00	Bayesian Approach to Spectrum Adjustment with Covariance Filter.
BAYES	Abstract	P00205 DP010 00	User's Guide for A General-Purpose Computer Code System for Fitting a Functional Form to Experimental Data.
BCG	Abstract	C00578 C0170 00	A Code For Calculating Pointwise Neutron Spectra and Criticality in Fast Reactor Cells.
BEACON MOD3	Abstract	P00402 CDCMF 00	Code System for Thermal-Hydraulic Analysis of Nuclear Reactor Containments.
BEBC	Abstract	C00077 I7090 00	Electron Bremsstrahlung Penetration Code for Space Vehicles.
BED	Abstract	C00078 I7090 00	Electron Penetration Code for Space Vehicles.
BERMUDA	Abstract	C00616 FV260 03	Discrete Ordinates Code System for Shielding Analysis for Use with Fusion and Fission Reactors.
BEST-5	Abstract	P00591 I0370 00	Power Reactor Fuel Cycle Optimization by Bellman Method.
BETA II	Abstract	C00117 C6600 00	Monte Carlo Bremsstrahlung and Electron Transport Analysis in Geometry.
BETA II	Abstract	C00117 I0360 00	Monte Carlo Bremsstrahlung and Electron Transport Analysis in Geometry.
BETA-S 6	Abstract	C00657 MNYCP 01	Code System to Calculate Multigroup Beta-Ray Spectra.
BFR USSO	Abstract	P00449 C0176 00	Code System for Common Cause Failure Data Analysis.
BIGGI	Abstract	C00066 I3675 00	Numerical Gamma-Ray Transport Code for Plane or Spherical Multilayer Geometry.
BIGGI	Abstract	C00066 U1108 00	Numerical Gamma-Ray Transport Code for Plane or Spherical Multilayer Geometry.
BIGGI-4T	Abstract	C00780 I0360 00	Gamma Transport in Multi-Region Shield in Planar or Spherical Geometry.
BISON 1.5	Abstract	C00464 HM200 00	One-Dimensional Discrete Ordinate Transport and Burnup Calculation Code System.
BISON-C	Abstract	C00659 MNYWS 00	One-Dimensional Discrete Ordinate Transport and Burnup Calculation Code System.
BLOCKAGE V2.5R	Abstract	P00377 IBMPC 00	Code System to Calculate Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in a BWR.
BLT-FEMWATER USSO	Abstract	C00633 PC386 00	Code System to Solve for Release and Transport of Contaminants through Saturated/Unsaturated Media.
BMC-MG	Abstract	C00291 C6600 00	Multigroup Monte Carlo Neutron and Gamma-Ray Shielding Code System for Plutonium.
BOLD VENTURE IV	Abstract	C00459 I3033 00	A Reactor Analysis Code System.
BON	Abstract	P00173 I0360 00	A Code System for Unfolding Multisphere Spectrometer Neutron Measurements.
BOREHOLE-EB6.8-MG	Abstract	D00268 MNYCP 00	Multi-Group Cross-Section Library for Deterministic and Monte Carlo Codes.
BOT3P-5.3	Abstract	P00530 MNYCP 02	Code System for 2D and 3D Mesh Generation and Graphical Display of Geometry and Results for Radiation Transport Codes.
BOXER	Abstract	C00766 MNYWS 00	Fine-flux Cross Section Condensation, 2D Few Group Diffusion and Transport Burnup Calculations
BP	Abstract	D00008 I0360 00	Data for Selected Shielding Benchmark Problems Specified in ORNL-RSIC-25, Shielding Benchmark Problems.
BPPC	Abstract	C00076 I7090 00	Proton Penetration Codes for Space Vehicles.
BREESE-II	Abstract	P00143 I3033 00	Auxiliary Routines for Implementing the Albedo Option in the MORSE Monte Carlo Code System.
BREMRAD	Abstract	C00031 I7090 00	External and Internal Bremsstrahlung Calculation Code.
BRHGAM	Abstract	C00350 I3033 00	Monte Carlo Estimation of Absorbed Dose from X-Ray Sources in Phantom Man.
BRMSTK	Abstract	P00044 C6600 00	CSEWG Integral Data Testing Shielding Experiment Code System.
BRMSTK	Abstract	P00044 I3691 00	CSEWG Integral Data Testing Shielding Experiment Code System.
BSPRP2	Abstract	P00372 IRISC 00	Code System to Process DORT Boundary-Flux Files.
BUCORST	Abstract	P00339 PC386 00	A Code to Prepare Burnup-Dependent Multigroup Nuclear Reactor Source Terms.
BUGENDF70.BOLIB	Abstract	D00262 PCX86 00	ENDF/B-VII.0 Broad-Group Coupled Cross Section Library for LWR Shielding & Pressure Vessel Dosimetry Applications.
BUGJEFF311.BOLIB	Abstract	D00254 MNYCP 01	JEFF-3.1.1 Broad-Group Coupled Cross Section Library For LWR Shielding & Pressure Vessel Dosimetry Applications.
BUGLE-80	Abstract	D00075 IBMPC 03	Coupled Neutron, Gamma-Ray Group Cross Section Library Derived from ENDF/B-VI for LWR Shielding and Pressure Vessel Dosimetry Applications.
BUGLE-80	Abstract	D00075 PC386 01	Coupled Neutron, Gamma-Ray Group Cross Section Library Derived from ENDF/B-VI for LWR Shielding and Pressure Vessel Dosimetry Applications.
BUGLE-93	Abstract	D00175 ALLCP 01	Coupled Neutron, Gamma-Ray Group Cross Section Library Derived from ENDF/B-VI for LWR Shielding and Pressure Vessel Dosimetry Applications.
BUGLE-96	Abstract	D00185 ALLCP 00	Coupled Neutron, Gamma-Ray Group Cross Section Library Derived from ENDF/B-VI for LWR Shielding and Pressure Vessel Dosimetry Applications.
BULK_C-12	Abstract	C00738 PC586 00	Code System to Estimate Neutron and Photon Effective Dose Rates from Medium Energy Protons or Carbon Ions Through Concrete or Concrete/Iron.
BULK-I	Abstract	P00574 PCX86 00	Radiation Shielding Tool for Proton Accelerator Facilities.
BURD	Abstract	P00582 IBMPC 00	Bayesian Estimation in Data Analysis of Probabilistic Safety Assessment.
BURP-2	Abstract	C00237 C6600 00	Calculation of Buildup and Decay of Radioactive Fission Products.
BUSH	Abstract	C00333 I0360 00	A Code to Calculate Radiation Doses Inside Buildings from Routine Releases of Radionuclides to the Atmosphere.
BUTTERCUP	Abstract	C00779 MNYCP 00	A Dual-Layer Photon Buildup Factor Code.
BWR-LTAS	Abstract	C00485 I3033 01	A Boiling Water Reactor Long-Term Accident Simulation Code.

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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.