SCALE 6.3.0 User Manual

SCALE is a comprehensive modeling and simulation suite for nuclear safety analysis and design developed and maintained by Oak Ridge National Laboratory under contract with the U.S. Nuclear Regulatory Commission, U.S. Department of Energy, and the National Nuclear Security Administration to perform reactor physics, criticality safety, radiation shielding, and spent fuel characterization for nuclear facilities and transportation/storage package designs.

Visit the SCALE website for additional information.

SCALE

• 1. Introduction
  • 1.1. Organization
  • 1.2. SCALE 6.3 Updates by Product
    • 1.2.1. Fulcrum
    • 1.2.2. CSAS
    • 1.2.3. VADER
    • 1.2.4. MAVRIC
    • 1.2.5. TRITON
    • 1.2.6. Polaris
    • 1.2.7. ORIGEN
    • 1.2.8. ORIGAMI
    • 1.2.9. XSProc
    • 1.2.10. DATA
    • 1.2.11. Sampler
    • 1.2.12. TSUNAMI
    • 1.2.13. AMPX
    • 1.2.14. Omnibus
  • 1.3. Using SCALE
    • 1.3.1. Running SCALE from Fulcrum
    • 1.3.2. Running SCALE from the Command Line
  • 1.4. User Guidance and Technical Assistance
  • 1.5. Code Availability
  • 1.6. History
  • 1.7. Acknowledgements
• 2. Criticality Safety
  • 2.1. CSAS: Control Module For Enhanced Criticality Safety Analysis Sequences With KENO
    • 2.1.1. Acknowledgments
    • 2.1.2. Introduction
    • 2.1.3. Sequence Capabilities
      • 2.1.3.1. Multigroup limitations
      • 2.1.3.2. Continuous energy limitations
    • 2.1.4. Input Data Guide
      • 2.1.4.1. XSProc data
      • 2.1.4.2. CSAS input data
        • 2.1.4.2.1. Definitions data
        • 2.1.4.2.2. Tallies data
        • 2.1.4.2.3. Mesh tally output files
      • 2.1.4.3. KENO data
    • 2.1.5. Description of Output
      • 2.1.5.1. Program verification information
      • 2.1.5.2. Mixture table
      • 2.1.5.3. Cross section processing summary
    • 2.1.6. Warning and error messages
    • 2.1.7. Sample problems
      • 2.1.7.1. CSAS5 sample problems
        • 2.1.7.1.1. CSAS5 sample problem 1: k_eff calculation
        • 2.1.7.1.2. CSAS5 Sample problem 8: k\(_{\infty}\) for a pebble bed fuel
      • 2.1.7.2. CSAS6 sample problems
        • 2.1.7.2.1. CSAS6 Sample problem 1: Aluminum 30 Degree Pipe Angle Intersection
        • 2.1.7.2.2. CSAS6 Sample problem 2: Plexiglas Cross
        • 2.1.7.2.3. CSAS6 Sample problem 3: Sphere
        • 2.1.7.2.4. CSAS6 Sample problem 4: Sphere Models Using Chords and Mirror Albedos
        • 2.1.7.2.5. CSAS6 Sample problem 5: Sphere Models Using Chords and Mirror Albedos
        • 2.1.7.2.6. CSAS6 Sample problem 6: Sphere Models Using Chords and Mirror Albedos (Eighth Sphere)
        • 2.1.7.2.7. CSAS6 Sample problem 7: Grotesque without the Diaphragm
        • 2.1.7.2.8. CSAS6 Sample problem 8 Infinite Array of MOX and UO2 Assemblies
  • 2.2. CSAS-Shift: Criticality Safety Analysis Sequence with Shift
    • 2.2.1. Introduction
    • 2.2.2. CSAS-Shift Input Requirements
    • 2.2.3. Sequence Capabilities
      • 2.2.3.1. Multigroup limitations
      • 2.2.3.2. Continuous-energy limitations
      • 2.2.3.3. Unsupported Capabilities
    • 2.2.4. Input Data Guide
      • 2.2.4.1. KENO input data in CSAS-Shift
        • 2.2.4.1.1. Parameter data
        • 2.2.4.1.2. Geometry data
          • 2.2.4.1.2.1. Random geometry
        • 2.2.4.1.3. Start data
    • 2.2.5. Notes to CSAS-Shift Users
    • 2.2.6. CSAS-Shift Output
      • 2.2.6.1. Shift output
        • 2.2.6.1.1. Program verification information
        • 2.2.6.1.2. General problem information
        • 2.2.6.1.3. Input Warnings
        • 2.2.6.1.4. Tables of parameter data
        • 2.2.6.1.5. Energy boundaries data
        • 2.2.6.1.6. Mixing table data edits
        • 2.2.6.1.7. Geometry data edits
        • 2.2.6.1.8. Volume information
        • 2.2.6.1.9. Initial source edits
        • 2.2.6.1.10. K-effectives by generation
        • 2.2.6.1.11. Final k-effective edit
        • 2.2.6.1.12. Plot of average k-effective by generations run and by generations skipped
        • 2.2.6.1.13. Shannon Entropy Diagnostics
        • 2.2.6.1.14. Fission densities
        • 2.2.6.1.15. Flux Edit
        • 2.2.6.1.16. Final results table
        • 2.2.6.1.17. Final timing report table
  • 2.3. Example Applications of CSAS6
    • 2.3.1. Run KENO-VI using CSAS6
    • 2.3.2. Run KENO-VI containing cell-weighted mixtures
    • 2.3.3. Run KENO-VI containing multiple unit cells
  • 2.4. DEVC: Denovo EigenValue Calculation
    • 2.4.1. Introduction
    • 2.4.2. Sequence input
      • 2.4.2.1. Parameters block
      • 2.4.2.2. Grid geometry block
      • 2.4.2.3. Macromaterial block
        • 2.4.2.3.1. Ray tracing
        • 2.4.2.3.2. Point testing
        • 2.4.2.3.3. Example
      • 2.4.2.4. Starting sources block
    • 2.4.3. Sequence Output
      • 2.4.3.1. Using the mesh file viewer
      • 2.4.3.2. Viewing the starting source
    • 2.4.4. Sample Problems
  • 2.5. KMART5 and KMART6: Postprocessors for KENO V.A and KENO-VI
    • 2.5.1. Introduction
    • 2.5.2. KMART Input Data
    • 2.5.3. KMART Sample Input
  • 2.6. C5toC6: Input File Conversion Programs for CSAS
    • 2.6.1. Introduction
    • 2.6.2. Description and Input Guide
• 3. Reactor Physics
  • 3.1. TRITON: A Multipurpose Transport, Depletion, And Sensitivity and Uncertainty Analysis Module
    • 3.1.1. Introduction
    • 3.1.2. Overview of TRITON Sequences
      • 3.1.2.1. Cross section processing sequence (T-XSEC)
      • 3.1.2.2. Transport sequences (T-XSDRN, T-NEWT)
      • 3.1.2.3. Depletion sequences (T-DEPL, T-DEPL-1D, T5-DEPL, T6-DEPL, T5-DEPL-SHIFT, T6-DEPL-SHIFT)
        • 3.1.2.3.1. Predictor-corrector depletion process
        • 3.1.2.3.2. Lattice physics analysis
    • 3.1.3. Input Description
      • 3.1.3.1. Cross section processing
        • 3.1.3.1.1. Combined two-region and S_N cross section processing
        • 3.1.3.1.2. User-defined Dancoff factors
      • 3.1.3.2. Transport sequences
      • 3.1.3.3. Depletion sequences input
        • 3.1.3.3.1. BURNDATA block
        • 3.1.3.3.2. BRANCH block
        • 3.1.3.3.3. BRANCH block with user-defined Dancoff factors
        • 3.1.3.3.4. DEPLETION block
          • 3.1.3.3.4.1. Basic DEPLETION block format
          • 3.1.3.3.4.2. ORIGEN depletion options
          • 3.1.3.3.4.3. Cross section processing simplification using ASSIGN
        • 3.1.3.3.5. TIMETABLE block
          • 3.1.3.3.5.1. Temperature and density
          • 3.1.3.3.5.2. Material swap
          • 3.1.3.3.5.3. Material flow
        • 3.1.3.3.6. OPUS block
          • 3.1.3.3.6.1. Selection of materials for OPUS processing
          • 3.1.3.3.6.2. Specification of stacked OPUS cases
        • 3.1.3.3.7. FGXS block
        • 3.1.3.3.8. TALLIES and DEFINITIONS block
      • 3.1.3.4. ALIAS block
        • 3.1.3.4.1. COMPOSITION block aliases
        • 3.1.3.4.2. CELLDATA block aliases
        • 3.1.3.4.3. DEPLETION block aliases
        • 3.1.3.4.4. TIMETABLE block aliases
        • 3.1.3.4.5. BRANCH block aliases
        • 3.1.3.4.6. NEWT MATERIAL block aliases
        • 3.1.3.4.7. KEEP_OUTPUT block
      • 3.1.3.5. TRITON control parameters
        • 3.1.3.5.1. Check mode: parm=check
        • 3.1.3.5.2. Multigroup cross section processing options
        • 3.1.3.5.3. Creating a broad group library: parm=weight, parm=(weight=N)
        • 3.1.3.5.4. Inclusion of additional nuclides for depletion: parm=(addnux=N)
        • 3.1.3.5.5. Few-group reaction cross section calculation control for continuous energy depletion: parm=(cxm=N)
        • 3.1.3.5.6. Infinite dilution cutoff control: parm=(infdcutoff=X)
        • 3.1.3.5.7. Override of the maximum number of days per depletion subinterval: PARM=(MAXDAYS=N)
    • 3.1.4. Output Files Created by TRITON
      • 3.1.4.1. Standard composition restart files
      • 3.1.4.2. Lattice physics parameters
      • 3.1.4.3. ORIGEN binary library files (.f33)
      • 3.1.4.4. ORIGEN binary concentration file (.f71)
      • 3.1.4.5. Binary mesh response files (.3dmap)
      • 3.1.4.6. Binary Shift output file (.h5)
    • 3.1.5. Output Description
      • 3.1.5.1. Control parameter edit
      • 3.1.5.2. T-XSEC output
      • 3.1.5.3. T-NEWT and T-XSDRN output
      • 3.1.5.4. Depletion sequence output
        • 3.1.5.4.1. Burnup history summary (all depletion sequences)
        • 3.1.5.4.2. Embedded transport model output
        • 3.1.5.4.3. System mass balance table
        • 3.1.5.4.4. Power balance tables
          • 3.1.5.4.4.1. ORIGEN binary concentration file listing
    • 3.1.6. TRITON Sample Cases
      • 3.1.6.1. TRITON sample problem 1: triton1.inp
      • 3.1.6.2. TRITON sample problem 2: triton2.inp
      • 3.1.6.3. TRITON sample problem 3: triton3.inp
        • 3.1.6.3.1. TRITON sample problem 4: triton4.inp
      • 3.1.6.4. TRITON sample problem 5: triton5.inp
      • 3.1.6.5. TRITON sample problem 6: triton6.inp
      • 3.1.6.6. TRITON sample problem 7: triton7.inp
      • 3.1.6.7. TRITON sample problem 8: triton8.inp
      • 3.1.6.8. TRITON sample problem 10: triton10.inp
      • 3.1.6.9. TRITON sample problem 11: triton11.inp
      • 3.1.6.10. TRITON sample problem 12: triton12.inp
      • 3.1.6.11. TRITON6 sample problem 1: triton6-1.inp
    • 3.1.7. Appendices
      • 3.1.7.1. XSDRN Model Block Description
        • 3.1.7.1.1. XSDRN PARAMETER block
        • 3.1.7.1.2. XSDRN MATERIAL block
        • 3.1.7.1.3. XSDRN COLLAPSE block
      • 3.1.7.2. Data Structure for Cross Section Database File xfile016
      • 3.1.7.3. The Flexible Branch Block
  • 3.2. POLARIS - 2D Light Water Reactor Lattice Physics Module
    • 3.2.1. Introduction
    • 3.2.2. SCALE 6.3 Polaris Input Updates
    • 3.2.3. Setup
      • 3.2.3.1. title - case title lines
      • 3.2.3.2. library - nuclear data libraries
    • 3.2.4. Geometry
      • 3.2.4.1. geometry<ASSM> – assembly
      • 3.2.4.2. geometry<REFL> - reflector
      • 3.2.4.3. channel - coolant channel
      • 3.2.4.4. hgap - half distance between assemblies
      • 3.2.4.5. box - channel box geometry
      • 3.2.4.6. pin - pincell comprised of nested geometry zones of variable shape
      • 3.2.4.7. pinmap - pin layout
      • 3.2.4.8. control<RODLET> - RCCA-type layout
      • 3.2.4.9. control<BLADE> - BWR control blade
      • 3.2.4.10. insert - insert layout
      • 3.2.4.11. slab - slab geometry
      • 3.2.4.12. cross - cross geometry
      • 3.2.4.13. dxmap and dymap - pin-by-pin displacement maps
      • 3.2.4.14. mesh - advanced material dependent meshing options
      • 3.2.4.15. detector - insert a detector geometry
    • 3.2.5. Materials
      • 3.2.5.1. material - material initialization
      • 3.2.5.2. composition<NUM|WT> – general atom/wt fraction
      • 3.2.5.3. composition<FORM> - general chemical formula
      • 3.2.5.4. composition<CONC> - general number density
      • 3.2.5.5. composition<LW> - borated light water
      • 3.2.5.6. composition<UOX> -UO₂ fuel
      • 3.2.5.7. composition<UN> - UN fuel
      • 3.2.5.8. composition<ENRU> – enriched uranium
      • 3.2.5.9. composition library (pre-defined)
      • 3.2.5.10. property<SOLP> - soluble poison by weight
      • 3.2.5.11. property<DOPANT> - fuel dopant by weight
      • 3.2.5.12. property<TWOPHASE> - density property used to control two phase mixtures
      • 3.2.5.13. deplete - material depletion and decay
      • 3.2.5.14. basis - power basis materials
      • 3.2.5.15. shield - cross section self-shielding expansion specification
    • 3.2.6. State
      • 3.2.6.1. power - total power
      • 3.2.6.2. bu - initiate calculation with cumulative burnups
      • 3.2.6.3. bui - initiate calculation with cumulative burnups (with restart)
      • 3.2.6.4. dbu - initiate calculation with incremental burnups
      • 3.2.6.5. t - initiate calculation by cumulative time
      • 3.2.6.6. ti - initiate calculation by cumulative time (with restart)
        • 3.2.6.6.1. dt - initiate calculation by incremental time
      • 3.2.6.7. branch - instantaneous change
      • 3.2.6.8. history - time-dependent history
      • 3.2.6.9. add<MNAME> - material branch
      • 3.2.6.10. add<INAME> - insert/control branch
      • 3.2.6.11. add<GNAME> - geometry branch
    • 3.2.7. Options
      • 3.2.7.1. option<KEFF> - eigenvalue
      • 3.2.7.2. option<ESSM> - embedded self-shielding
      • 3.2.7.3. option<BOND> - Bondarenko search
      • 3.2.7.4. option<DEPL> - depletion
      • 3.2.7.5. option<CRITSPEC> - critical spectrum
      • 3.2.7.6. option<PRINT> - printing
      • 3.2.7.7. option<FG> - few-group cross section generation
      • 3.2.7.8. option<RUN> - run time
      • 3.2.7.9. option<GEOM> - geometry options
      • 3.2.7.10. option<GAMMA> - gamma transport calculation
      • 3.2.7.11. option<DATA> – data libraries
    • 3.2.8. System
      • 3.2.8.1. system<PWR> - pressurized water reactor
      • 3.2.8.2. system<BWR> - boiling water reactor
    • 3.2.9. Sample Problems
    • 3.2.10. Appendices
      • 3.2.10.1. SCALE 6.2 Polaris Input Format
        • 3.2.10.1.1. box – channel box
        • 3.2.10.1.2. pin – pin or pincell
        • 3.2.10.1.3. bu – initiate calculation with cumulative burnups
        • 3.2.10.1.4. dbu – initiate calculation with incremental burnups
        • 3.2.10.1.5. t – initiate calculation by cumulative time
        • 3.2.10.1.6. dt – initiate calculation by incremental time
        • 3.2.10.1.7. option<ESSM> - embedded self-shielding
        • 3.2.10.1.8. option<FG> – few-group cross section generation
        • 3.2.10.1.9. state<MNAME> – material state
        • 3.2.10.1.10. state<INAME> – insert/control state
        • 3.2.10.1.11. state<GNAME> – geometry state
• 4. Radiation Shielding
  • 4.1. MAVRIC: Monaco with Automated Variance Reduction using Importance Calculations
    • 4.1.1. Introduction
    • 4.1.2. CADIS Methodology
      • 4.1.2.1. Overview of CADIS
      • 4.1.2.2. Multiple sources with CADIS
      • 4.1.2.3. Multiple tallies with CADIS
      • 4.1.2.4. Forward-weighted CADIS
      • 4.1.2.5. MAVRIC Implementation of CADIS
        • 4.1.2.5.1. Denovo
        • 4.1.2.5.2. Monaco
        • 4.1.2.5.3. Running MAVRIC
    • 4.1.3. MAVRIC input
      • 4.1.3.1. Composition block
      • 4.1.3.2. SGGP geometry blocks
      • 4.1.3.3. Other blocks shared with Monaco
      • 4.1.3.4. Importance map block
        • 4.1.3.4.1. Constructing a mesh for the S_N calculation
        • 4.1.3.4.2. Macromaterials for S_N geometries
          • 4.1.3.4.2.1. Ray Tracing
          • 4.1.3.4.2.2. Point Testing
          • 4.1.3.4.2.3. Example
        • 4.1.3.4.3. Optimizing source/detector problems
        • 4.1.3.4.4. Multiple adjoint sources
        • 4.1.3.4.5. Options for Denovo \(S_n\) calculations
        • 4.1.3.4.6. Starting with an existing adjoint flux file
        • 4.1.3.4.7. Forward-weighting the adjoint source
        • 4.1.3.4.8. Forward weighting with an existing forward flux file
        • 4.1.3.4.9. Using the importance map
        • 4.1.3.4.10. Other notes on importance map calculations
    • 4.1.4. MAVRIC output
      • 4.1.4.1. Main text output file
      • 4.1.4.2. Additional output files
    • 4.1.5. Sample problems
      • 4.1.5.1. Graphite shielding measurements with CADIS
        • 4.1.5.1.1. Input file
        • 4.1.5.1.2. Output
      • 4.1.5.2. Dose rates outside of a simple cask
        • 4.1.5.2.1. Geometry and materials
        • 4.1.5.2.2. Sources and responses
        • 4.1.5.2.3. Analog calculation
        • 4.1.5.2.4. SAS4 calculations
        • 4.1.5.2.5. Calculations using CADIS
        • 4.1.5.2.6. MAVRIC input files
        • 4.1.5.2.7. Neutron source/neutron response results
        • 4.1.5.2.8. Photon source/photon response results
      • 4.1.5.3. Gamma-ray litho-density logging tool using FW-CADIS
        • 4.1.5.3.1. Input file
        • 4.1.5.3.2. Output
      • 4.1.5.4. AOS-100 using FW-CADIS and continuous-energy transport
        • 4.1.5.4.1. Input file
        • 4.1.5.4.2. Output file
      • 4.1.5.5. Independent spent fuel storage installation
        • 4.1.5.5.1. Source term
        • 4.1.5.5.2. Input file
        • 4.1.5.5.3. Output
      • 4.1.5.6. TN24-P spent fuel cask
        • 4.1.5.6.1. Input file
        • 4.1.5.6.2. Output
  • 4.2. MAVRIC CAAS Capability
    • 4.2.1. Introduction
    • 4.2.2. Methods
    • 4.2.3. User Input
      • 4.2.3.1. KENO-VI input
      • 4.2.3.2. Mesh tally to mesh source conversion
      • 4.2.3.3. MAVRIC input
    • 4.2.4. Example problem
      • 4.2.4.1. KENO-VI criticality and fission source distribution
      • 4.2.4.2. MAVRIC transport calculations
        • 4.2.4.2.1. Detector doses using CADIS
        • 4.2.4.2.2. Dose map using FW-CADIS
    • 4.2.5. Summary
  • 4.3. MAVRIC Utilities
    • 4.3.1. Introduction
    • 4.3.2. Utilities working with Monaco mesh tally (3DMAP) files
    • 4.3.3. Utilities for working with DENOVO binary flux (*.dff) files
    • 4.3.4. Utilities for working with DENOVO *.varscl (a TORT format) files
    • 4.3.5. Miscellaneous utilities
  • 4.4. MAVRIC Advanced Features
    • 4.4.1. Alternate normalization of the importance map and biased source
    • 4.4.2. Importance maps with directional information
      • 4.4.2.1. Approaches incorporating directional information
      • 4.4.2.2. Directionally dependent weight windows without directional source biasing
      • 4.4.2.3. Directionally dependent weight windows with directional source biasing
      • 4.4.2.4. Using space/energy/angle CADIS in MAVRIC
      • 4.4.2.5. Example problem
        • 4.4.2.5.1. CADIS
        • 4.4.2.5.2. Angular CADIS 1 - without a biased source angular dist.
        • 4.4.2.5.3. Angular CADIS 2 - with a biased source angular dist.
    • 4.4.3. University of Michigan methods for global variance reduction
      • 4.4.3.1. Weight windows using only forward estimates of flux
        • 4.4.3.1.1. Global flux weight windows
        • 4.4.3.1.2. Global response weight windows
        • 4.4.3.1.3. Implementation in MAVRIC
      • 4.4.3.2. Methods using forward and adjoint estimates
        • 4.4.3.2.1. Source/detector problems
        • 4.4.3.2.2. Source-region problems
        • 4.4.3.2.3. Global response problem
      • 4.4.3.3. Implementation in MAVRIC
        • 4.4.3.3.1. Example problems
        • 4.4.3.3.2. CADIS
        • 4.4.3.3.3. Becker 1 - flux optimization
        • 4.4.3.3.4. Becker 2 - response optimization
        • 4.4.3.3.5. A global problem
        • 4.4.3.3.6. FW-CADIS
        • 4.4.3.3.7. GRWW
        • 4.4.3.3.8. Becker source/region
        • 4.4.3.3.9. Becker - global
      • 4.4.3.4. Other special options for the importance map block input
    • 4.4.4. Using MAVRIC to run fixed-source Denovo calculations
      • 4.4.4.1. Optional Denovo parameters
      • 4.4.4.2. Forward source preparations
      • 4.4.4.3. Adjoint source preparation
      • 4.4.4.4. Other notes
      • 4.4.4.5. MAVRIC utilities for Denovo
      • 4.4.4.6. Example problem
        • 4.4.4.6.1. Forward
        • 4.4.4.6.2. Adjoint
• 5. Depletion, Activation, and Spent Fuel Source Terms
  • 5.1. ORIGEN: Neutron activation, transmutation, fission product generation, & radiation source term calculation
    • 5.1.1. Acknowledgements
    • 5.1.2. Version Information
      • 5.1.2.1. Version 6.3 (2021)
      • 5.1.2.2. Version 6.2 (2016)
      • 5.1.2.3. Version 6.1 (2011)
        • 5.1.2.3.1. ORIGEN
        • 5.1.2.3.2. COUPLE
        • 5.1.2.3.3. ARP
        • 5.1.2.3.4. OPUS
    • 5.1.3. Method of solution
      • 5.1.3.1. Methodology
        • 5.1.3.1.1. Generation of Problem-dependent Transition Matrix
        • 5.1.3.1.2. Solution of the Depletion/Decay Equations
          • 5.1.3.1.2.1. MATREX
          • 5.1.3.1.2.2. CRAM
        • 5.1.3.1.3. Power Calculation
        • 5.1.3.1.4. Decay Emission Sources Calculation
          • 5.1.3.1.4.1. Neutron Sources
          • 5.1.3.1.4.2. Alpha Sources
          • 5.1.3.1.4.3. Beta Sources
          • 5.1.3.1.4.4. Photon Sources
        • 5.1.3.1.5. Library Interpolation
          • 5.1.3.1.5.1. Lagrangian Interpolation
          • 5.1.3.1.5.2. Cubic Spline Interpolation
    • 5.1.4. ORIGEN Family of Modules
    • 5.1.5. ORIGEN
      • 5.1.5.1. Key Features
        • 5.1.5.1.1. Nuclide Specification and ORIGEN Sub-libraries
        • 5.1.5.1.2. Physical Units in Calculations
        • 5.1.5.1.3. Saving Results
      • 5.1.5.2. Input Description
        • 5.1.5.2.1. Calculation Case (case)
        • 5.1.5.2.2. Transition Matrix Specification (lib)
        • 5.1.5.2.3. Material Specification (mat)
        • 5.1.5.2.4. Operating History (power, flux, time)
        • 5.1.5.2.5. Printing Options (print)
          • 5.1.5.2.5.1. Inventories by nuclide and element
          • 5.1.5.2.5.2. Radiological Emissions (alpha, beta, gamma, neutron)
        • 5.1.5.2.6. Saving Results (save)
        • 5.1.5.2.7. Decay Emission Calculations (alpha, beta, gamma, neutron)
          • 5.1.5.2.7.1. Neutron source calculation
          • 5.1.5.2.7.2. Gamma source calculation
          • 5.1.5.2.7.3. Alpha and beta source calculation
        • 5.1.5.2.8. Processing Options (processing)
        • 5.1.5.2.9. Bounds Block
        • 5.1.5.2.10. Solver Block
        • 5.1.5.2.11. Options Block
        • 5.1.5.2.12. Library Building Block build_lib
          • 5.1.5.2.12.1. Nuclide Block build_lib/nuclide
          • 5.1.5.2.12.2. Decay Data Block build_lib/decay
          • 5.1.5.2.12.3. Neutron Data Block build_lib/neutron
          • 5.1.5.2.12.4. Data Cutoffs
        • 5.1.5.2.13. Sensitivity Calculation Block sens
          • 5.1.5.2.13.1. Sensitivity output tables
          • 5.1.5.2.13.2. Sensitivity output files
    • 5.1.6. ARP
      • 5.1.6.1. Input Description
      • 5.1.6.2. ARPDATA.TXT listing file
    • 5.1.7. OPUS
      • 5.1.7.1. Key Features
      • 5.1.7.2. Input Description
        • 5.1.7.2.1. Nuclide/element plots
        • 5.1.7.2.2. Spectra plots
        • 5.1.7.2.3. Selection of plotting data
      • 5.1.7.3. Plot File Formats
    • 5.1.8. Examples
      • 5.1.8.1. Decay of ²³⁸U
      • 5.1.8.2. ²⁵²Cf neutron Emission Spectrum
      • 5.1.8.3. Simple Fuel Irradiation Plus Decay
      • 5.1.8.4. Three Cycles of Irradiation Plus Decay
      • 5.1.8.5. Load Isotopics from an f71 File
      • 5.1.8.6. Continuous Feed and Removal
      • 5.1.8.7. Calculate Fuel \(\left(\alpha,n \right)\) Emissions in a Glass Matrix
      • 5.1.8.8. Create an ORIGEN Decay Library from a Decay Resource
      • 5.1.8.9. Create an ORIGEN Reaction Library
      • 5.1.8.10. Create an ORIGEN Activation Library
      • 5.1.8.11. Create an ORIGEN Library with User-Supplied Cross Sections
      • 5.1.8.12. Printing library cross-section values
        • 5.1.8.12.1. Print the Cross Section Values on an ORIGEN Library with OBIWAN
        • 5.1.8.12.2. Print the Cross Section Values on an ORIGEN Library in ORIGEN
      • 5.1.8.13. Ranking Contribution to Toxicity
      • 5.1.8.14. Spectrum plots with OPUS
        • 5.1.8.14.1. Photon Spectrum Plot
        • 5.1.8.14.2. Neutron Spectrum Plot
      • 5.1.8.15. Isotopic Weight Percentages for Uranium and Plutonium During Decay
      • 5.1.8.16. User-Specified Response Function in OPUS
    • 5.1.9. Appendices
      • 5.1.9.1. PRISM
      • 5.1.9.2. ARPLIB
      • 5.1.9.3. XSECLIST
      • 5.1.9.4. COUPLE
        • 5.1.9.4.1. Key Features
          • 5.1.9.4.1.1. AMPX multi-group libraries
          • 5.1.9.4.1.2. Nuclide Specification
          • 5.1.9.4.1.3. Adding new transitions and user-defined transitions
          • 5.1.9.4.1.4. Unit numbers and Aliases
        • 5.1.9.4.2. Input Description
          • 5.1.9.4.2.1. Block1: titles, unit numbers, and case controls.
          • 5.1.9.4.2.2. Block2: nuclides with fission yields and weighting flux spectrum
          • 5.1.9.4.2.3. Block3: array dimensions for decay library creation
          • 5.1.9.4.2.4. Block6: number of user-defined transition coefficients
          • 5.1.9.4.2.5. Block8: user-defined transition coefficients
  • 5.2. OBIWAN: A tool for viewing and manipulating Origen binary files
    • 5.2.1. obiwan info
    • 5.2.2. obiwan view
      • 5.2.2.1. Output formatting
        • 5.2.2.1.1. ORIGEN nuclide ID formatting
        • 5.2.2.1.2. Format options for Origen data resources
        • 5.2.2.1.3. Format options for Origen concentrations files
      • 5.2.2.2. Data filter options
      • 5.2.2.3. Output control options
      • 5.2.2.4. Data manipulation options
      • 5.2.2.5. Usage examples
        • 5.2.2.5.1. Displaying a table of loss cross-section data
        • 5.2.2.5.2. Output transitions to a graphical format
        • 5.2.2.5.3. Output a JSON-based inventory interface file
    • 5.2.3. obiwan tag
      • 5.2.3.1. Viewing tags on on a file
      • 5.2.3.2. Adding tags to a file
      • 5.2.3.3. Deleting tags on a file
    • 5.2.4. obiwan convert
    • 5.2.5. obiwan diff
      • 5.2.5.1. Obiwan diff examples
    • 5.2.6. obiwan interp
      • 5.2.6.1. Interpolation usage examples
    • 5.2.7. obiwan patch
      • 5.2.7.1. obiwan patch usage examples
  • 5.3. ORIGEN Reactor Libraries
    • 5.3.1. Description of ORIGEN Reactor Libraries in SCALE
    • 5.3.2. How to Generate ORIGEN Cross-Section Libraries
    • 5.3.3. Appendices
      • 5.3.3.1. SCALE/ORIGEN Library Generator (SLIG)
        • 5.3.3.1.1. Quick Start Directions
        • 5.3.3.1.2. Advanced Options
        • 5.3.3.1.3. Template File Rules and Examples
          • 5.3.3.1.3.1. UOX fuel parameters
          • 5.3.3.1.3.2. MOX fuel parameters
          • 5.3.3.1.3.3. Documentation header
        • 5.3.3.1.4. Troubleshooting
        • 5.3.3.1.5. Code Information
  • 5.4. ORIGAMI: A Code for Computing Assembly Isotopics with ORIGEN
    • 5.4.1. Acknowledgments
    • 5.4.2. Introduction
    • 5.4.3. Computational Methods
      • 5.4.3.1. ORIGAMI assembly model
      • 5.4.3.2. Definition of initial composition
      • 5.4.3.3. Restart cases
      • 5.4.3.4. Definition of power distribution
      • 5.4.3.5. Computation of neutron and gamma energy spectra
    • 5.4.4. ORIGAMI Input Description
      • 5.4.4.1. Case and identifier information
      • 5.4.4.2. Options block
      • 5.4.4.3. Fuel composition block
      • 5.4.4.4. Power history block
      • 5.4.4.5. Source options block
      • 5.4.4.6. Output print-options block
      • 5.4.4.7. Input data arrays
    • 5.4.5. ORIGAMI Input/Output Files
      • 5.4.5.1. Generation of SCALE standard composition data file
      • 5.4.5.2. MCNP data files
      • 5.4.5.3. Decay heat calculation
      • 5.4.5.4. ORIGEN results files
      • 5.4.5.5. Plotting features
    • 5.4.6. Parallel Execution on Linux Clusters
    • 5.4.7. Sample Problems
      • 5.4.7.1. Sample problem 1: fully lumped assembly model
      • 5.4.7.2. Sample problem 2: lumped axial depletion assembly model
      • 5.4.7.3. Sample problem 3: restart decay calculation for lumped axial depletion assembly model
      • 5.4.7.4. Sample problem 4: Simplified 3D multi-pin model
      • 5.4.7.5. Sample problem 5: PWR 3D assembly model
• 6. Sensitivity and Uncertainty Analysis
  • 6.1. TSUNAMI-1D: Control Module for One-Dimensional Cross-Section Sensitivity and Uncertainty
    • 6.1.1. ABSTRACT
    • 6.1.2. ACKNOWLEDGMENTS
    • 6.1.3. Introduction
      • 6.1.3.1. TSUNAMI-1D Techniques
    • 6.1.4. TSUNAMI-1D Input Description
      • 6.1.4.1. Analytical sequence specification record
      • 6.1.4.2. XSProc
      • 6.1.4.3. Model problem data
        • 6.1.4.3.1. Geometry data
        • 6.1.4.3.2. Parameter data
      • 6.1.4.4. Sensitivity and uncertainty calculation data
        • 6.1.4.4.1. Response definition data
          • 6.1.4.4.1.1. Single-mixture flux response function
          • 6.1.4.4.1.2. Multiple-mixture flux response
          • 6.1.4.4.1.3. Single-mixture, single-nuclide, microscopic cross-section response
          • 6.1.4.4.1.4. Single-mixture, single-nuclide, macroscopic cross-section response
          • 6.1.4.4.1.5. Single-mixture, multiple-nuclide, macroscopic cross-section response
          • 6.1.4.4.1.6. Multiple-mixture, single-nuclide, macroscopic cross-section response
          • 6.1.4.4.1.7. Multiple-mixture, multiple-nuclide, macroscopic cross-section response
        • 6.1.4.4.2. System response definition data
        • 6.1.4.4.3. SAMS data
        • 6.1.4.4.4. HTML and user-input covariance data
      • 6.1.4.5. Input termination
    • 6.1.5. Example Problems
      • 6.1.5.1. INFHOMMEDIUM sample problem
      • 6.1.5.2. Multiregion sample problem
      • 6.1.5.3. GPT sample problem
    • 6.1.6. Appendices
      • 6.1.6.1. XSDRNPM Data File Formats
      • 6.1.6.2. XSDRNPM forward output file
      • 6.1.6.3. XSDRNPM adjoint output file
  • 6.2. TSUNAMI-3D: Control Module for Three-Dimensional Cross Section Sensitivity and Uncertainty Analysis for Criticality
    • 6.2.1. Introduction
    • 6.2.2. Multigroup TSUNAMI-3D Techniques
    • 6.2.3. Continuous-Energy TSUNAMI-3D Techniques
      • 6.2.3.1. CE TSUNAMI methodology
        • 6.2.3.1.1. IFP methodology
        • 6.2.3.1.2. CLUTCH methodology
      • 6.2.3.2. CE TSUNAMI Generalized Perturbation Theory capability
      • 6.2.3.3. CE TSUNAMI sequence description
    • 6.2.4. TSUNAMI-3D Input Description
      • 6.2.4.1. Analytical sequence specification record
      • 6.2.4.2. Title data
      • 6.2.4.3. XSProc Execution
      • 6.2.4.4. KENO V.A or KENO-VI problem description
      • 6.2.4.5. Sensitivity calculation data
      • 6.2.4.6. Input termination
    • 6.2.5. Sample problems
      • 6.2.5.1. Generating reference direct perturbation sensitivity coefficients
      • 6.2.5.2. Simple MG Sample Problem
        • 6.2.5.2.1. Multigroup sample problem with spatial flux mesh
      • 6.2.5.3. Complex sample problem
        • 6.2.5.3.1. Loosely coupled sample problem
      • 6.2.5.4. CE TSUNAMI Sample Problem
  • 6.3. TSUNAMI Utility Modules
    • 6.3.1. TSUNAMI-IP
      • 6.3.1.1. Global integral indices
        • 6.3.1.1.1. Integral index c_k
        • 6.3.1.1.2. Integral index c\(_r\)
        • 6.3.1.1.3. Integral index E
        • 6.3.1.1.4. Integral index G
      • 6.3.1.2. Nuclide-reaction specific integral indices
        • 6.3.1.2.1. Nuclide-reaction specific integral index g
        • 6.3.1.2.2. Extended \(c_k\)
        • 6.3.1.2.3. Extended c\(_r\)
      • 6.3.1.3. Penalty assessment
      • 6.3.1.4. Other parameters
        • 6.3.1.4.1. Uncertainty information
        • 6.3.1.4.2. Completeness parameter
        • 6.3.1.4.3. Composite sensitivity data
        • 6.3.1.4.4. Non-coverage
      • 6.3.1.5. Miscellaneous options
        • 6.3.1.5.1. VADER input files
        • 6.3.1.5.2. Covariance data directory listing
        • 6.3.1.5.3. HTML output
        • 6.3.1.5.4. Case sensitive input
        • 6.3.1.5.5. Print filenames
        • 6.3.1.5.6. \(c_k\) and E differences
          • 6.3.1.5.6.1. Plots
        • 6.3.1.5.7. Absolute sensitivity option
      • 6.3.1.6. User input
        • 6.3.1.6.1. Parameter data
        • 6.3.1.6.2. Reaction data
        • 6.3.1.6.3. User input covariance data
        • 6.3.1.6.4. Application, experiment, and response data
        • 6.3.1.6.5. Reactions excluded from \(c_r\)
        • 6.3.1.6.6. HTML data
        • 6.3.1.6.7. Example TSUNAMI-IP input
      • 6.3.1.7. Example PROBLEM
        • 6.3.1.7.1. Input description
        • 6.3.1.7.2. Output Description
        • 6.3.1.7.3. HTML output description
    • 6.3.2. BONAMIST
    • 6.3.3. References
    • 6.3.4. Appendices
      • 6.3.4.1. Data File Formats
        • 6.3.4.1.1. Format of TSUNAMI-A sensitivity data file
        • 6.3.4.1.2. Format of TSUNAMI-B sensitivity data file
        • 6.3.4.1.3. Format of HDF5-based sensitivity data file
        • 6.3.4.1.4. Format of SENLIB.SEN data file
        • 6.3.4.1.5. Format of BONAMIST.SEN data file
        • 6.3.4.1.6. COVERX format
        • 6.3.4.1.7. HTML colors
  • 6.4. Sampler: Statistical Uncertainty Analysis with SCALE Sequences
    • 6.4.1. Introduction
      • 6.4.1.1. Uncertainty analysis with stochastic versus perturbation methods
    • 6.4.2. Methodology
      • 6.4.2.1. Definition of input data perturbations
      • 6.4.2.2. Nuclear data perturbations for multigroup calculations
      • 6.4.2.3. Depletion data perturbations
      • 6.4.2.4. Model data perturbations
      • 6.4.2.5. Importance Ranking \(R^2\) Methodology
    • 6.4.3. Input Description
      • 6.4.3.1. Overall input structure
        • 6.4.3.1.1. Cases and sequences
        • 6.4.3.1.2. Importing input data from external files
      • 6.4.3.2. Configuration parameters
      • 6.4.3.3. Sampler responses
        • 6.4.3.3.1. OPUS PLT file responses
        • 6.4.3.3.2. TRITON homogenized cross-section responses
        • 6.4.3.3.3. Standard composition file responses
        • 6.4.3.3.4. ORIGEN concentration (F71) responses
        • 6.4.3.3.5. Generic regular expression (GREP) responses
        • 6.4.3.3.6. Sampled variable values
        • 6.4.3.3.7. Quick response definition overview
      • 6.4.3.4. Saving files
      • 6.4.3.5. Parametric studies
      • 6.4.3.6. Geometry and material perturbations
        • 6.4.3.6.1. Variable definition
        • 6.4.3.6.2. Distribution types
        • 6.4.3.6.3. Dependent variables (expressions)
        • 6.4.3.6.4. Using placeholders
        • 6.4.3.6.5. Using SIREN expressions
      • 6.4.3.7. Response analysis
        • 6.4.3.7.1. Pearson Correlation Example
        • 6.4.3.7.2. Correlation Matrix Example
        • 6.4.3.7.3. Squared Correlation Example
      • 6.4.3.8. Converting a standard SCALE input to a Sampler input
    • 6.4.4. Execution Details
      • 6.4.4.1. General workflow
      • 6.4.4.2. File management
      • 6.4.4.3. Parallel execution
      • 6.4.4.4. Behavior when encountering errors
    • 6.4.5. Example Problems and Output Description
      • 6.4.5.1. Output description
        • 6.4.5.1.1. Main text output
          • 6.4.5.1.1.1. Sampler banner
          • 6.4.5.1.1.2. Input parameters echo
          • 6.4.5.1.1.3. SCALE run overview
          • 6.4.5.1.1.4. Response tables
        • 6.4.5.1.2. CSV tables
        • 6.4.5.1.3. Sampling histograms and running averages
        • 6.4.5.1.4. Response histories
      • 6.4.5.2. Sample problems
        • 6.4.5.2.1. Sample problem 1
        • 6.4.5.2.2. Sample problem 2
        • 6.4.5.2.3. Sample problem 3
          • 6.4.5.2.3.1. Sample problem 4
        • 6.4.5.2.4. Sample problem 5
        • 6.4.5.2.5. Sample problem 6
        • 6.4.5.2.6. Sample problem 7
    • 6.4.6. SCALE Input Retrieval ENgine (SIREN)
    • 6.4.7. Expression Operators and Functions for Sampler
    • 6.4.8. Guidelines for Running Sampler in Parallel
  • 6.5. VADER: Trending Analysis for Code/Data Validation
    • 6.5.1. Theory
    • 6.5.2. Input
    • 6.5.3. Detailed Input
      • 6.5.3.1. data
      • 6.5.3.2. title
      • 6.5.3.3. parameters
      • 6.5.3.4. trend_values
      • 6.5.3.5. methods
      • 6.5.3.6. tests
    • 6.5.4. Available Methods
      • 6.5.4.1. USL1 - Confidence Band with Administrative Margin
      • 6.5.4.2. USL2 - Single-Sided Uniform Width Closed Interval Approach
      • 6.5.4.3. CR6698 - Single-Sided Lower Tolerance Band
      • 6.5.4.4. NonParametric - Historical Non-Parametric Method
      • 6.5.4.5. Parametric - Historical Parametric Method
    • 6.5.5. Available Tests
      • 6.5.5.1. chisq - \(\chi^2\) Normality Test
      • 6.5.5.2. t-test - Trend Significance t-test
      • 6.5.5.3. anderson_darling - Anderson-Darling Normality Test
    • 6.5.6. Available Parameters
      • 6.5.6.1. tsunami
      • 6.5.6.2. extrapolate
      • 6.5.6.3. fit_confidence
      • 6.5.6.4. admin_margin
      • 6.5.6.5. xrange
      • 6.5.6.6. proportion_confidence
      • 6.5.6.7. proportion
      • 6.5.6.8. f_p
      • 6.5.6.9. normal_p
      • 6.5.6.10. chi_p
      • 6.5.6.11. weighted
      • 6.5.6.12. confidence
      • 6.5.6.13. proportion_of_pop
      • 6.5.6.14. use_npm
  • 6.6. SAMS: Sensitivity Analysis Module for SCALE
    • 6.6.1. Introduction
    • 6.6.2. Theory
      • 6.6.2.1. Explicit sensitivity coefficient generation
      • 6.6.2.2. Implicit sensitivity coefficient generation
        • 6.6.2.2.1. Complete sensitivity coefficient
      • 6.6.2.3. Summary of sensitivity coefficients calculated by SAMS
      • 6.6.2.4. Uncertainty analysis
      • 6.6.2.5. Problem characterization
        • 6.6.2.5.1. Generalized perturbation theory
    • 6.6.3. SAMS Input Description
      • 6.6.3.1. Analytical sequence specification record
      • 6.6.3.2. SAMS input data
      • 6.6.3.3. Data files required by SAMS
      • 6.6.3.4. Example input
    • 6.6.4. Sample Problems And Output Description
      • 6.6.4.1. Example problem using XSDRNPM
      • 6.6.4.2. Example problem using KENO V.a
    • 6.6.5. Error And Warning Messages
      • 6.6.5.1. Error Messages
      • 6.6.5.2. Warning Messages
  • 6.7. TSAR: Tool for Sensitivity Analysis of Reactivity Responses
    • 6.7.1. Introduction
    • 6.7.2. Methodology
      • 6.7.2.1. Reactivity sensitivity coefficients
      • 6.7.2.2. Reactivity uncertainty analysis
      • 6.7.2.3. Cross-section-covariance data
    • 6.7.3. Input Description
      • 6.7.3.1. Parameter data
      • 6.7.3.2. User-input covariance data
      • 6.7.3.3. HTML data
    • 6.7.4. Sample Problem and Output Description
      • 6.7.4.1. Input and text output
    • 6.7.5. HTML Output
  • 6.8. TSURFER: An Adjustment Code to Determine Biases and Uncertainties in Nuclear System Responses by Consolidating Differential Data and Benchmark Integral Experiments
    • 6.8.1. Introduction
      • 6.8.1.1. Application to validation studies
      • 6.8.1.2. Types of responses
    • 6.8.2. Sources of Response Uncertainty
      • 6.8.2.1. Class-A uncertainties (numerical)
      • 6.8.2.2. Class-B uncertainties (modeling/experimental)
      • 6.8.2.3. Class-C uncertainties (nuclear data)
    • 6.8.3. Analysis Procedure
      • 6.8.3.1. Functional relation to other SCALE modules
      • 6.8.3.2. Guidelines for TSURFER analysis
      • 6.8.3.3. Required data for TSURFER
    • 6.8.4. TSURFER Computation Methodology
      • 6.8.4.1. Representation of experimental uncertainty components
      • 6.8.4.2. Generalized linear least-squares equations
        • 6.8.4.2.1. Consistency relations and chi-square filtering
        • 6.8.4.2.2. Expressions for computational bias
      • 6.8.4.3. Expressions for response similarity parameters
        • 6.8.4.3.1. The E similarity parameter (sim_type=E)
        • 6.8.4.3.2. The G similarity parameter (sim_type=G)
        • 6.8.4.3.3. The C similarity parameter (sim_type=C)
      • 6.8.4.4. Convergence of reference application response
    • 6.8.5. TSURFER Input Description
      • 6.8.5.1. Parameter block
      • 6.8.5.2. RESPONSE block
      • 6.8.5.3. COVARIANCE block
      • 6.8.5.4. HTML block
      • 6.8.5.5. CORR block
    • 6.8.6. Sample Problem Input and Output Description
      • 6.8.6.1. Input and text output
      • 6.8.6.2. HTML Output
    • 6.8.7. Appendices
      • 6.8.7.1. TSURFER Appendix A: Sensitivity/Uncertainty Notation
        • 6.8.7.1.1. Basic variables
        • 6.8.7.1.2. Sensitivity Relations
        • 6.8.7.1.3. Absolute covariances
        • 6.8.7.1.4. Relative covariances
        • 6.8.7.1.5. Mixed absolute-relative covariances
        • 6.8.7.1.6. Correlation matrices
• 7. Material Specification and Cross Section Processing
  • 7.1. XSPROC: The Material and Cross Section Processing Module for SCALE
    • 7.1.1. Introduction
    • 7.1.2. Techniques
      • 7.1.2.1. Overview of XSProc procedures
      • 7.1.2.2. Standard composition material processing
      • 7.1.2.3. Unit cells for MG resonance self-shielding
        • 7.1.2.3.1. INFHOMMEDIUM (infinite homogeneous medium) Treatment
        • 7.1.2.3.2. LATTICECELL Treatment
        • 7.1.2.3.3. MULTIREGION Treatment
        • 7.1.2.3.4. DOUBLEHET Treatment
      • 7.1.2.4. Cell weighting of MG cross sections
    • 7.1.3. XSPROC Input Data Guide
      • 7.1.3.1. XSProc data checking and resonance processing options
      • 7.1.3.2. XSProc input data
      • 7.1.3.3. Standard composition specification data
      • 7.1.3.4. Unit cell specification for infinite homogeneous problems
      • 7.1.3.5. Unit cell specification for LATTICECELL problems
      • 7.1.3.6. Unit cell specification for MULTIREGION cells
      • 7.1.3.7. Unit cell specification for doubly heterogeneous (DOUBLEHET) cells
      • 7.1.3.8. Optional MORE DATA parameter data
      • 7.1.3.9. Optional CENTRM DATA parameter data
    • 7.1.4. Appendices
      • 7.1.4.1. XSProc: Standard Composition Examples
        • 7.1.4.1.1. Standard composition fundamentals
        • 7.1.4.1.2. Basic standard composition specifications
        • 7.1.4.1.3. User-defined (arbitrary) chemical compound specifications
        • 7.1.4.1.4. User-defined (arbitrary) mixture/alloy specifications
        • 7.1.4.1.5. Fissile solution specifications
        • 7.1.4.1.6. Combinations of standard composition materials to define a mixture
        • 7.1.4.1.7. Combinations of user-defined compound and user-defined mixture/alloy to define a mixture
        • 7.1.4.1.8. Combinations of solutions to define a mixture
        • 7.1.4.1.9. Combinations of basic and user-defined standard compositions to define a mixture
        • 7.1.4.1.10. Combinations of basic and solution standard compositions to define a mixture
        • 7.1.4.1.11. Combinations of user-defined compound and solution to define a mixture
      • 7.1.4.2. XSProc Standard Composition Examples
        • 7.1.4.2.1. Infinite homogeneous medium unit cell data
        • 7.1.4.2.2. LATTICECELL unit cell data
        • 7.1.4.2.3. MULTIREGION unit cell data
        • 7.1.4.2.4. DOUBLEHET unit cell data
        • 7.1.4.2.5. Optional parameter data
        • 7.1.4.2.6. CENTRM DATA examples
      • 7.1.4.3. Examples of Complete XSProc Input Data
        • 7.1.4.3.1. Infinite homogeneous medium input data
        • 7.1.4.3.2. LATTICECELL input data
        • 7.1.4.3.3. MULTIREGION input data
        • 7.1.4.3.4. DOUBLEHET input data
        • 7.1.4.3.5. Two methods of specifying a fissile solution
        • 7.1.4.3.6. Multiple unit cells in a single problem
        • 7.1.4.3.7. Multiple fissile mixtures in a single unit cell
        • 7.1.4.3.8. Cell weighting an infinite homogeneous problem
        • 7.1.4.3.9. Cell weighting a LATTICECELL problem
        • 7.1.4.3.10. Cell weighting a MULTIREGION problem
  • 7.2. Standard Composition Library
    • 7.2.1. Introduction
    • 7.2.2. The Standard Composition Library
    • 7.2.3. Table of Fissile Solutions
  • 7.3. BONAMI: Resonance Self-Shielding by the Bondarenko Method
    • 7.3.1. Introduction
    • 7.3.2. Bondarenko Self-Shielding Theory
      • 7.3.2.1. Parameterized Flux Spectra
      • 7.3.2.2. Self-Shielded Cross Section Data in SCALE Libraries
      • 7.3.2.3. Background Cross Section Options in BONAMI
      • 7.3.2.4. Self-Shielded Cross Sections for Heterogeneous Media
    • 7.3.3. Interpolation Scheme
    • 7.3.4. Input Instructions
      • 7.3.4.1. Notes on input
    • 7.3.5. Sample Problem
  • 7.4. CENTRM: A Neutron Transport Code for Computing Continuous-Energy Spectra in General One-Dimensional Geometries and Two-Dimensional Lattice Cells
    • 7.4.1. Introduction
      • 7.4.1.1. Description of problem solved
      • 7.4.1.2. Nuclear data required for CENTRM
      • 7.4.1.3. Code assumptions and features
    • 7.4.2. Theory and Analytical Models
      • 7.4.2.1. Energy/lethargy ranges for MG and PW calculations
      • 7.4.2.2. The Boltzmann equation for neutron transport
      • 7.4.2.3. Legendre moments of the scattering source
        • 7.4.2.3.1. Epithermal Elastic Scatter
        • 7.4.2.3.2. Epithermal Inelastic Scatter
        • 7.4.2.3.3. Thermal Scatter
        • 7.4.2.3.4. Bound thermal kernels
          • 7.4.2.3.4.1. Free gas thermal kernels
      • 7.4.2.4. Sub-moment expansion of the epithermal scattering source
        • 7.4.2.4.1. Characteristics and Properties of the Sub-Moment Expansion
        • 7.4.2.4.2. Scattering moments expressed with cumulative integral operator
      • 7.4.2.5. Multigroup Boltzmann equation
        • 7.4.2.5.1. Multigroup data for CENTRM calculation
        • 7.4.2.5.2. Conversion of multigroup fluxes to pseudo-pointwise values
      • 7.4.2.6. The Boltzmann equation within the PW range
        • 7.4.2.6.1. Scattering sources for the PW range
        • 7.4.2.6.2. Downscatter source from high region of the UMR to the PW range (SHI)
        • 7.4.2.6.3. Scattering sources from UMR transition region and epithermal PW range
        • 7.4.2.6.4. PW thermal scatter source
        • 7.4.2.6.5. Downscatter source from the epithermal PW range to the LMR
        • 7.4.2.6.6. Thermal scatter sources from LMR and PW range
      • 7.4.2.7. Determination of energy mesh for PW flux calculation
      • 7.4.2.8. CENTRM cross sections and fixed sources
        • 7.4.2.8.1. CENTRM PW cross-section libraries
        • 7.4.2.8.2. Linearization of MG cross sections and fixed sources
    • 7.4.3. Available Methods for Solving Transport Equation
      • 7.4.3.1. Discrete ordinates
        • 7.4.3.1.1. Homogenized infinite medium
      • 7.4.3.2. Zonewise infinite medium
      • 7.4.3.3. Collision probability method
      • 7.4.3.4. P₁ (“Diffusion Theory”) method
      • 7.4.3.5. Two-region (2R) method
      • 7.4.3.6. Method of characteristics for a 2D unit cell
    • 7.4.4. CENTRM Input Data
      • 7.4.4.1. CENTRM data notes
      • 7.4.4.2. CENTRM I/O files
      • 7.4.4.3. Description of the CENTRM CE cross section file
      • 7.4.4.4. Description of the CENTRM output PW flux file
    • 7.4.5. Example Case
      • 7.4.5.1. CENTRM input for example case
      • 7.4.5.2. CENTRM output for example case
    • 7.4.6. CENTRM PW library and flux file formats
      • 7.4.6.1. CENTRM CE cross section file
      • 7.4.6.2. CENTRM output PW flux file
    • 7.4.7. CENTRM Error Messages
  • 7.5. PMC: A Program to Produce Multigroup Cross Sections Using Pointwise Energy Spectra from CENTRM
    • 7.5.1. Introduction
      • 7.5.1.1. Description of PMC input nuclear data
      • 7.5.1.2. Description of PMC input pointwise flux data
    • 7.5.2. Code Features
      • 7.5.2.1. Options for treatment of 1-D cross sections
      • 7.5.2.2. Spatial averaging of 1D cross sections
      • 7.5.2.3. Energy ranges for multigroup weighting
      • 7.5.2.4. Options for treatment of 2-D cross sections
    • 7.5.3. Calculation of Problem-Dependent Multigroup Cross Sections
      • 7.5.3.1. 1-D cross sections
      • 7.5.3.2. 2-D scattering cross sections
      • 7.5.3.3. Problem-dependent fission spectra
      • 7.5.3.4. Definition of background cross sections
    • 7.5.4. PMC Input Data
      • 7.5.4.1. Notes for PMC users
    • 7.5.5. Example Case
      • 7.5.5.1. PMC input for example case
      • 7.5.5.2. PMC output for example case
    • 7.5.6. Formats of Data Files
    • 7.5.7. Appendices
      • 7.5.7.1. Alphabetical Index of Subroutines
      • 7.5.7.2. Alphabetical Index of Modules
  • 7.6. CHOPS: Module to Compute Pointwise Disadvantage Factors and Produce a Cell-Homogenized CENTRM Library
    • 7.6.1. Introduction
    • 7.6.2. CHOPS Input Data
    • 7.6.3. CHOPS I/O units
    • 7.6.4. CHOPS Sample Input
  • 7.7. CRAWDAD: Module to Produce CENTRM-Formatted Continuous-Energy Nuclear Data Libraries
    • 7.7.1. Introduction
    • 7.7.2. CRAWDAD Input Data
    • 7.7.3. CRAWDAD Sample Input
  • 7.8. MCDancoff: Monte-Carlo based Dancoff Factor Calculation
    • 7.8.1. Introduction
    • 7.8.2. Input data description
    • 7.8.3. Calculation and use of 3D Dancoff factors
    • 7.8.4. Example Case
  • 7.9. CAJUN: Module for Combining and Manipulating CENTRM Continuous-Energy Libraries
    • 7.9.1. Introduction
    • 7.9.2. CAJUN Input Data
    • 7.9.3. CAJUN I/O Units
• 8. Monte Carlo Transport
  • 8.1. KENO: A Monte Carlo Criticality Program
    • 8.1.1. ACKNOWLEDGMENTS
    • 8.1.2. Introduction to KENO
    • 8.1.3. KENO Data Guide
      • 8.1.3.1. Keno input outline
      • 8.1.3.2. Procedure for data input
      • 8.1.3.3. Title and parameter data
      • 8.1.3.4. Geometry data
        • 8.1.3.4.1. UNITS
          • 8.1.3.4.1.1. UNIT initialization
          • 8.1.3.4.1.2. Shape
          • 8.1.3.4.1.3. COM=
          • 8.1.3.4.1.4. HOLE
          • 8.1.3.4.1.5. ARRAY
          • 8.1.3.4.1.6. REPLICATE and REFLECTOR
          • 8.1.3.4.1.7. MEDIA
          • 8.1.3.4.1.8. BOUNDARY
      • 8.1.3.5. ARRAY Data
        • 8.1.3.5.1. ARRAY Parameters
          • 8.1.3.5.1.1. ARA=
          • 8.1.3.5.1.2. GBL=
          • 8.1.3.5.1.3. PRT=
          • 8.1.3.5.1.4. NUX=, NUY=, NUZ=
          • 8.1.3.5.1.5. TYPE=
          • 8.1.3.5.1.6. COM=
        • 8.1.3.5.2. ARRAY orientation data
          • 8.1.3.5.2.1. LOOP Construct
          • 8.1.3.5.2.2. FILL Construct
      • 8.1.3.6. Albedo data
      • 8.1.3.7. Biasing or weighting data
      • 8.1.3.8. Start data
        • 8.1.3.8.1. ASCII Start Data File Format
      • 8.1.3.9. Extra 1-D XSECS IDs data
      • 8.1.3.10. Mixing table data
      • 8.1.3.11. Plot data
      • 8.1.3.12. Energy group boundary data
      • 8.1.3.13. Volume data
      • 8.1.3.14. Grid geometry data
      • 8.1.3.15. Reaction data
    • 8.1.4. Notes for KENO Users
      • 8.1.4.1. Data entry
        • 8.1.4.1.1. Multiple and scattered entries in the mixing table
        • 8.1.4.1.2. Multiple entries in geometry data
      • 8.1.4.2. Default logical unit numbers for KENO
      • 8.1.4.3. Parameter input
      • 8.1.4.4. Cross sections
        • 8.1.4.4.1. Use a mixed cross section Monte Carlo format library
        • 8.1.4.4.2. Use an AMPX working format library
        • 8.1.4.4.3. Number of scattering angles
        • 8.1.4.4.4. Cross section message cutoff
      • 8.1.4.5. Mixing table
      • 8.1.4.6. Geometry Considerations
        • 8.1.4.6.1. Use of holes in the geometry
        • 8.1.4.6.2. Nesting holes
        • 8.1.4.6.3. Multiple arrays
        • 8.1.4.6.4. Arrays and holes
        • 8.1.4.6.5. Triangular pitched arrays in KENO-VI
        • 8.1.4.6.6. Triangular pitched Arrays in KENO V.a
        • 8.1.4.6.7. Dodecahedral pitched arrays
      • 8.1.4.7. Alternative sample problem mockups
        • 8.1.4.7.1. Sample Problem C.12, First Alternative
        • 8.1.4.7.2. Sample Problem C.12, Second Alternative
        • 8.1.4.7.3. Sample Problem C.13, Alternative
      • 8.1.4.8. Initial starting distributions with Start data
      • 8.1.4.9. Biasing or weighting data for multigroup mode
      • 8.1.4.10. Color plots
      • 8.1.4.11. KENO Multiple Mesh and Mesh-based Quantity Specifications
      • 8.1.4.12. Random sequence
      • 8.1.4.13. Matrix k-effective
      • 8.1.4.14. Deviations
      • 8.1.4.15. Generation time and lifetime
      • 8.1.4.16. Energy of the Average Lethargy of Fission
    • 8.1.5. Description of Output
      • 8.1.5.1. Program verification information
      • 8.1.5.2. Tables of parameter data
      • 8.1.5.3. Unprocessed geometry input data
      • 8.1.5.4. Table of data sets used in the problem
      • 8.1.5.5. Table of additional information
      • 8.1.5.6. Cross section data edits for the continuous energy mode
      • 8.1.5.7. Mixing table data edits
        • 8.1.5.7.1. Multigroup mode mixing table data edit
        • 8.1.5.7.2. Continuous-energy mode mixing table data edit
      • 8.1.5.8. Albedo cross section correspondence
      • 8.1.5.9. 1-D macroscopic cross sections
      • 8.1.5.10. Extra 1-d cross sections
      • 8.1.5.11. 2-D macroscopic cross sections
      • 8.1.5.12. Probabilities and angles
      • 8.1.5.13. Energy boundaries
      • 8.1.5.14. Array summary
      • 8.1.5.15. Geometry data edits
        • 8.1.5.15.1. KENO V.a geometry edit
        • 8.1.5.15.2. KENO-VI geometry edit
      • 8.1.5.16. Unit orientation description
      • 8.1.5.17. Volume information
        • 8.1.5.17.1. KENO V.a volume edit
        • 8.1.5.17.2. KENO-VI volume edit
      • 8.1.5.18. Mesh volumes output edit
      • 8.1.5.19. Grid definitions
      • 8.1.5.20. Biasing information
      • 8.1.5.21. Group-dependent weights
      • 8.1.5.22. Plot representation
      • 8.1.5.23. Initial source and final pretracking edits
      • 8.1.5.24. Reference center for flux moment/angular flux transform
      • 8.1.5.25. Print starting points
      • 8.1.5.26. K-effectives by generation
      • 8.1.5.27. Problem characterization edit
      • 8.1.5.28. Final k-effective edit
      • 8.1.5.29. Plot of average k-effective by generation run
      • 8.1.5.30. Plot of average k-effective by generations skipped
      • 8.1.5.31. Final edit of fissions, absorptions, and leakage
      • 8.1.5.32. Matrix k-effective by position index
      • 8.1.5.33. Fission production by position index matrix
      • 8.1.5.34. Source vector by position index
      • 8.1.5.35. Cofactor k-effective by position index
      • 8.1.5.36. Matrix k-effective by unit number
      • 8.1.5.37. Fission production by unit number matrix
      • 8.1.5.38. Source vector by unit number
      • 8.1.5.39. Cofactor k-effective by unit number
      • 8.1.5.40. Matrix k-effective by hole number
      • 8.1.5.41. Fission production by hole number matrix
      • 8.1.5.42. Source vector by hole number
      • 8.1.5.43. Cofactor k-effective by hole number
      • 8.1.5.44. Matrix k-effective by array number
      • 8.1.5.45. Fission production by array number matrix
      • 8.1.5.46. Source vector by array number
      • 8.1.5.47. Cofactor k-effective by array number
      • 8.1.5.48. Mesh tallies
      • 8.1.5.49. Reaction tally
      • 8.1.5.50. Source convergence diagnostics edit
      • 8.1.5.51. Fission density edit
      • 8.1.5.52. Flux edit
      • 8.1.5.53. Frequency distributions
      • 8.1.5.54. Summary of parallel performance
      • 8.1.5.55. Final results table
      • 8.1.5.56. HTML output
        • 8.1.5.56.1. HTML output: Program verification information
        • 8.1.5.56.2. HTML output: Messages
        • 8.1.5.56.3. HTML output: Tables of parameter data
        • 8.1.5.56.4. HTML output: Table of additional information
        • 8.1.5.56.5. HTML output: Mixing table data
        • 8.1.5.56.6. HTML output: 1D macroscopic cross sections
        • 8.1.5.56.7. HTML output: 2-D macroscopic cross sections
        • 8.1.5.56.8. HTML output: Probabilities and angles
        • 8.1.5.56.9. HTML output: Geometry data
        • 8.1.5.56.10. HTML output: Volume information
          • 8.1.5.56.10.1. KENO V.a
          • 8.1.5.56.10.2. KENO-VI
          • 8.1.5.56.10.3. Mesh volumes
        • 8.1.5.56.11. HTML output: Biasing information
        • 8.1.5.56.12. HTML output: Group-dependent weights
        • 8.1.5.56.13. HTML output: Plot representation
        • 8.1.5.56.14. HTML output: Initial source and final pretracking edits
        • 8.1.5.56.15. HTML output: Reference center for flux moment/angular flux tranform
        • 8.1.5.56.16. HTML output: K-effectives by generation
        • 8.1.5.56.17. HTML output: Problem characterization edit
        • 8.1.5.56.18. HTML output: Final k-effective edit
        • 8.1.5.56.19. HTML output: Final edit of fissions, absorptions, and leakage
        • 8.1.5.56.20. HTML output: Matrix k-effective by position index
        • 8.1.5.56.21. HTML output: Fission production by position index matrix
        • 8.1.5.56.22. HTML output: Source vector by position index
        • 8.1.5.56.23. HTML output: Cofactor k-effective by position index
        • 8.1.5.56.24. HTML output: Matrix k-effective, fission production, source vector and cofactor k-effective by unit number
        • 8.1.5.56.25. HTML output: Matrix k-effective, fission production, source vector and cofactor k-effective by hole number
        • 8.1.5.56.26. HTML output: Matrix k-effective, fission production, source vector and cofactor k-effective by array number
        • 8.1.5.56.27. HTML output: Fission density edit
        • 8.1.5.56.28. HTML output: Flux edit
        • 8.1.5.56.29. HTML output: Final results table
    • 8.1.6. Warning messages and error messages
      • 8.1.6.1. Messages
    • 8.1.7. Theory and Techniques
      • 8.1.7.1. The transport equation
      • 8.1.7.2. Continuous energy mode solution procedure
        • 8.1.7.2.1. Problem initialization
        • 8.1.7.2.2. Initial source distribution
        • 8.1.7.2.3. Collision site selection
        • 8.1.7.2.4. Collision treatment
        • 8.1.7.2.5. Fission treatment
        • 8.1.7.2.6. Sampling details
          • 8.1.7.2.6.1. Probability tables
          • 8.1.7.2.6.2. Equiprobable cross section bands
          • 8.1.7.2.6.3. Nonequiprobable cross section bands
        • 8.1.7.2.7. Kinematics data
          • 8.1.7.2.7.1. General procedures
          • 8.1.7.2.7.2. Exit angle cosine
          • 8.1.7.2.7.3. Exit energy
          • 8.1.7.2.7.4. Isotropic Angular Distributions With Energy Coupling
          • 8.1.7.2.7.5. Coherent and incoherent elastic scattering
          • 8.1.7.2.7.6. Elastic and discrete-level inelastic scattering
        • 8.1.7.2.8. Thermal scattering effects
        • 8.1.7.2.9. Doppler broadening rejection correction method
        • 8.1.7.2.10. Doppler broadening methods
      • 8.1.7.3. Multigroup mode solution procedure
        • 8.1.7.3.1. Collision treatment in KENO
        • 8.1.7.3.2. Fission point selection
        • 8.1.7.3.3. Biasing or weighting
        • 8.1.7.3.4. Differential albedos
      • 8.1.7.4. KENO Geometries
      • 8.1.7.5. Fluxes
      • 8.1.7.6. Reaction Rate and Few Group Micro Cross Section Calculations
      • 8.1.7.7. Source Convergence Diagnostics
        • 8.1.7.7.1. Shannon Entropy Statistics
        • 8.1.7.7.2. Source Convergence Diagnostic Input
    • 8.1.8. Appendices
      • 8.1.8.1. KENO V.a Shape Descriptions
      • 8.1.8.2. KENO VI Shape Descriptions
      • 8.1.8.3. KENO Sample Problems
        • 8.1.8.3.1. CSAS-MG data
        • 8.1.8.3.2. KENO V.a sample problem data
          • 8.1.8.3.2.1. Sample Problem 1 2C8 BARE
          • 8.1.8.3.2.2. Sample Problem 2 CASE 2C8 BARE WITH 8 UNIT TYPES MATRIX CALCULATION
          • 8.1.8.3.2.3. Sample Problem 3 2C8 15.24-CM PARAFFIN REFL
          • 8.1.8.3.2.4. Sample Problem 4 2C8 15.24-CM PARAFFIN REFL AUTOMATIC REFL
          • 8.1.8.3.2.5. Sample Problem 5 2C8 12-INCH PARAFFIN ALBEDO REFLECTOR
          • 8.1.8.3.2.6. Sample Problem 6 ONE 2C8 UNIT (SINGLE UNIT)
          • 8.1.8.3.2.7. Sample Problem 7 BARE 2C8 USING SPECULAR REFLECTION
          • 8.1.8.3.2.8. Sample Problem 8 INFINITELY LONG CYLINDER FROM 2C8 UNIT
          • 8.1.8.3.2.9. Sample Problem 9 INFINITE ARRAY OF 2C8 UNITS
          • 8.1.8.3.2.10. Sample Problem 10 2C8 BARE WRITE RESTART
          • 8.1.8.3.2.11. Sample Problem 11 2C8 BARE READ RESTART DATA
          • 8.1.8.3.2.12. Sample Problem 12 4 AQUEOUS 4 METAL
          • 8.1.8.3.2.13. Sample Problem 13 TWO CUBOIDS IN A CYLINDRICAL ANNULUS
          • 8.1.8.3.2.14. Sample Problem 14 U METAL CYLINDER IN AN ANNULUS
          • 8.1.8.3.2.15. Sample Problem 15 SMALL WATER REFLECTED SPHERE ON PLEXIGLAS COLLAR
          • 8.1.8.3.2.16. Sample Problem 16 UO2F2 INFINITE SLAB K-INFINITY
          • 8.1.8.3.2.17. Sample Problem 17 93% UO2F2 SOLUTION SPHERE ADJOINT CALCULATION
          • 8.1.8.3.2.18. Sample Problem 18 1F27 DEMONSTRATION OF OPTIONS
          • 8.1.8.3.2.19. Sample Problem 19 4 AQUEOUS 4 METAL ARRAY OF ARRAYS (SAMP PROB 12)
          • 8.1.8.3.2.20. Sample Problem 20 TRIANGULAR PITCHED ARRAY
          • 8.1.8.3.2.21. Sample Problem 21 PARTIALLY FILLED SPHERE
          • 8.1.8.3.2.22. Sample Problem 22 CASE 2C8 BARE WITH 3 NESTED HOLES, EACH IS EQUAL VOLUME
          • 8.1.8.3.2.23. Sample Problem 23 CASE 2C8 BARE AS STACKED CYLINDERS
          • 8.1.8.3.2.24. Sample Problem 24 CASE 2C8 BARE AS STACKED ROTATED CYLINDERS
          • 8.1.8.3.2.25. Sample Problem 25 CASE 2C8 BARE AS MIXED YHEMICYLINDERS
          • 8.1.8.3.2.26. Sample Problem 26 (KENO V.a ONLY) CASE 2C8 BARE AS MIXED ZHEMICYLINDERS WITH ORIGINS
          • 8.1.8.3.2.27. Sample Problem 27 (KENO V.a oONLY) CASE 2C8 BARE AS MIXED XHEMICYLINDERS WITH ORIGINS
          • 8.1.8.3.2.28. Sample Problem 28 (KENO V.a oONLY) CASE 2C8 BARE AS MIXED YHEMICYLINDERS WITH ORIGINS
          • 8.1.8.3.2.29. Sample Problem 29 BARE CRITICAL SPHERE 3.4420-IN. RADIUS
          • 8.1.8.3.2.30. Sample Problem 30 (KENO V.a ONLY) BARE CRITICAL SPHERE Z HEMISPHERE MODEL 3.4420-IN. RADIUS
          • 8.1.8.3.2.31. Sample Problem 31 (KENO V.a ONLY) BARE CRITICAL SPHERE X HEMISPHERE MODEL 3.4420-IN. RADIUS
          • 8.1.8.3.2.32. Sample Problem 32 (KENO V.a ONLY) BARE CRITICAL SPHERE Y HEMISPHERE MODEL 3.4420-IN. RADIUS
          • 8.1.8.3.2.33. Sample Problem 33 CRITICAL TRIANGULAR PITCHED ARRAY OF ANNULAR RODS
  • 8.2. Monaco: A Fixed-Source Monte Carlo Transport Code for Shielding Applications
    • 8.2.1. Introduction
    • 8.2.2. Monaco Capabilities
      • 8.2.2.1. Source Descriptions
        • 8.2.2.1.1. Distributions
        • 8.2.2.1.2. Spatial energy and directional attributes
        • 8.2.2.1.3. Monaco mesh source map files
      • 8.2.2.2. Tallies
        • 8.2.2.2.1. Tally statistics
        • 8.2.2.2.2. Statistical tests
        • 8.2.2.2.3. Point detector tallies
          • 8.2.2.2.3.1. Multigroup
          • 8.2.2.2.3.2. Continuous Energy
        • 8.2.2.2.4. Region tallies
        • 8.2.2.2.5. Mesh tallies
      • 8.2.2.3. Continuous Energy Transport
    • 8.2.3. Monaco Input Files
      • 8.2.3.1. Cross sections block
      • 8.2.3.2. Geometry block
      • 8.2.3.3. Array, volume, and plot blocks
      • 8.2.3.4. Definitions block
        • 8.2.3.4.1. Locations
        • 8.2.3.4.2. Response functions
        • 8.2.3.4.3. Grid geometries
        • 8.2.3.4.4. Cylindrical mesh geometries
        • 8.2.3.4.5. Distributions
        • 8.2.3.4.6. Energy boundaries
        • 8.2.3.4.7. Time boundaries
      • 8.2.3.5. Sources block
        • 8.2.3.5.1. Spatial distribution
        • 8.2.3.5.2. Energy distribution
        • 8.2.3.5.3. Directional distribution
        • 8.2.3.5.4. Using a Monaco mesh source map file
        • 8.2.3.5.5. Creating a mesh source
        • 8.2.3.5.6. Mesh source advanced features
      • 8.2.3.6. Tallies block
        • 8.2.3.6.1. Point detector tallies
        • 8.2.3.6.2. Region tallies
        • 8.2.3.6.3. Mesh tallies
      • 8.2.3.7. Parameter Block
      • 8.2.3.8. Biasing Block
        • 8.2.3.8.1. Forced collisions
        • 8.2.3.8.2. Weight windows
        • 8.2.3.8.3. Path-length stretching
        • 8.2.3.8.4. Mesh-based importance map
        • 8.2.3.8.5. Monaco input summary
    • 8.2.4. Monaco Output
      • 8.2.4.1. Main text output file
      • 8.2.4.2. Tally files
      • 8.2.4.3. Diagnostic files
      • 8.2.4.4. Mesh source saver files
      • 8.2.4.5. Statistical checks on point detector and region tallies
    • 8.2.5. Example Problems
      • 8.2.5.1. Neutron transmission through an iron sphere
        • 8.2.5.1.1. Input
        • 8.2.5.1.2. Output
      • 8.2.5.2. Neutrons through a heavy water sphere
        • 8.2.5.2.1. Input
        • 8.2.5.2.2. Output
      • 8.2.5.3. Activation rate from a neutron howitzer
        • 8.2.5.3.1. Input file
        • 8.2.5.3.2. Output
      • 8.2.5.4. Graphite shielding measurements
        • 8.2.5.4.1. Input file
        • 8.2.5.4.2. Output
      • 8.2.5.5. Simple shielding demonstration with line spectra
        • 8.2.5.5.1. Input file
        • 8.2.5.5.2. Output
• 9. Deterministic Transport
  • 9.1. XSDRNPM: A One-Dimensional Discrete-Ordinates Code for Transport Analysis
    • 9.1.1. Introduction
      • 9.1.1.1. Functions performed
        • 9.1.1.1.1. Background on XSDRNPM
      • 9.1.1.2. Applications in SCALE
        • 9.1.1.2.1. Notes on the use of various spectral calculational options
      • 9.1.1.3. Selection of output cross-section library formats
    • 9.1.2. Theory and Procedures
      • 9.1.2.1. One-dimensional discrete-ordinates theory
      • 9.1.2.2. Multigroup one-dimensional Boltzmann equation
      • 9.1.2.3. Scattering source term
        • 9.1.2.3.1. Slab and Spherical Geometries
        • 9.1.2.3.2. Cylindrical Geometry
      • 9.1.2.4. Discrete-ordinates difference equations
        • 9.1.2.4.1. Discrete-ordinates equation for a slab
        • 9.1.2.4.2. Discrete-ordinates equations for sphere and cylinder
        • 9.1.2.4.3. \(S_n\) quadratures for slabs
        • 9.1.2.4.4. \(S_n\) quadratures for spheres
        • 9.1.2.4.5. \(S_n\) quadratures for cylinders
      • 9.1.2.5. Weighted-difference formulation for discrete-ordinates equations
      • 9.1.2.6. Boundary conditions
      • 9.1.2.7. Fixed sources
      • 9.1.2.8. Dimension search calculations
        • 9.1.2.8.1. Zone-width search (IEVT = 4)
        • 9.1.2.8.2. Outer radius search (IEVT = 5)
        • 9.1.2.8.3. Buckling search (IEVT = 6)
        • 9.1.2.8.4. Search calculation strategy
      • 9.1.2.9. Alpa Search
        • 9.1.2.9.1. Alpha search
        • 9.1.2.9.2. Direct-buckling search
      • 9.1.2.10. Iteration and convergence tests
      • 9.1.2.11. Group banding (scaling rebalance)
      • 9.1.2.12. Buckling correction
      • 9.1.2.13. Void streaming correction
      • 9.1.2.14. Cross-section weighting
        • 9.1.2.14.1. “Cell Weighting”
        • 9.1.2.14.2. “Zone” weighting
        • 9.1.2.14.3. “Region” weighting
        • 9.1.2.14.4. “Inner-cell” weighting
        • 9.1.2.14.5. Multigroup weighting equations
        • 9.1.2.14.6. Transfer matrices
        • 9.1.2.14.7. Weighting of \(\bar{v}\)
        • 9.1.2.14.8. Transport cross sections
          • 9.1.2.14.8.1. Outscatter approximation (inconsistent method)
          • 9.1.2.14.8.2. Inscatter approximation (consistent method)
          • 9.1.2.14.8.3. Weighting function for transport cross section
      • 9.1.2.15. Adjoint calculations
        • 9.1.2.15.1. Generalized adjoint calculations
      • 9.1.2.16. Coupled neutron-photon calculations
      • 9.1.2.17. Diffusion theory option
      • 9.1.2.18. Infinite-medium theory option
      • 9.1.2.19. B_N theory option
    • 9.1.3. XSDRNPM Input Data
      • 9.1.3.1. Abbreviated XSDRNPM input description
    • 9.1.4. XSDRNPM Input/Output Assignments
    • 9.1.5. XSDRN Sample Problem
    • 9.1.6. Output Cross Sections
    • 9.1.7. Error messages
    • 9.1.8. Appendices
      • 9.1.8.1. Special XSDRNPM Files
        • 9.1.8.1.1. Activity file
        • 9.1.8.1.2. Balance table file
        • 9.1.8.1.3. Input and derived data file
      • 9.1.8.2. XSDRNPM Mixed Cross Sections
  • 9.2. NEWT: A New Transport Algorithm for Two-Dimensional Discrete-Ordinates Analysis in Non-Orthogonal Geometries
    • 9.2.1. Introduction
      • 9.2.1.1. How to use this manual
      • 9.2.1.2. Background
      • 9.2.1.3. Discrete-ordinates solution on an arbitrary grid
      • 9.2.1.4. Functions performed
    • 9.2.2. Theory and Procedures
      • 9.2.2.1. Boltzmann transport equation
      • 9.2.2.2. The step characteristic approximation
      • 9.2.2.3. The Extended Step Characteristic approach
        • 9.2.2.3.1. Cell properties and geometries
        • 9.2.2.3.2. Relationships between cells
        • 9.2.2.3.3. The set of characteristic directions
        • 9.2.2.3.4. Angular flux at a cell boundary
        • 9.2.2.3.5. Mapping a characteristic vector into the two-dimensional problem domain
        • 9.2.2.3.6. Neutron balance within a computational cell
      • 9.2.2.4. Coarse-mesh finite-difference acceleration
      • 9.2.2.5. Assembly discontinuity factors
    • 9.2.3. Input Formats
      • 9.2.3.1. Overview of newt data blocks
      • 9.2.3.2. Parameter block
        • 9.2.3.2.1. Convergence and acceleration parameters
        • 9.2.3.2.2. Output editing
        • 9.2.3.2.3. Angular quadrature
        • 9.2.3.2.4. Control options
          • 9.2.3.2.4.1. Geometry processing options
        • 9.2.3.2.5. Critical spectrum options
        • 9.2.3.2.6. File unit options
      • 9.2.3.3. Material Block
      • 9.2.3.4. Source block
      • 9.2.3.5. Collapse block
      • 9.2.3.6. Geometry block
        • 9.2.3.6.1. Bodies
          • 9.2.3.6.1.1. Shapes
          • 9.2.3.6.1.2. Cylinder
          • 9.2.3.6.1.3. Cuboid
          • 9.2.3.6.1.4. Hexprism and rhexprism
          • 9.2.3.6.1.5. Wedge
          • 9.2.3.6.1.6. Polygon
          • 9.2.3.6.1.7. Example of shape specifications
          • 9.2.3.6.1.8. Shape modifier commands
          • 9.2.3.6.1.9. ORIGIN
          • 9.2.3.6.1.10. Rotate
          • 9.2.3.6.1.11. Chord
          • 9.2.3.6.1.12. Com
          • 9.2.3.6.1.13. Sides
          • 9.2.3.6.1.14. Holes
          • 9.2.3.6.1.15. Array placement
        • 9.2.3.6.2. Media specifications
          • 9.2.3.6.2.1. Unit boundary
        • 9.2.3.6.3. Geometry block examples
          • 9.2.3.6.3.1. Simple pin cell
          • 9.2.3.6.3.2. Hexagonal assembly
          • 9.2.3.6.3.3. Advanced CANDU reactor ACR-700 assembly
        • 9.2.3.6.4. Summary of geometry specifications
          • 9.2.3.6.4.1. Unit definition statements
          • 9.2.3.6.4.2. Geometry modifiers
      • 9.2.3.7. Boundary conditions
        • 9.2.3.7.1. Boundary conditions descriptions
          • 9.2.3.7.1.1. Reflective boundary condition
          • 9.2.3.7.1.2. White boundary condition
          • 9.2.3.7.1.3. Vacuum boundary condition
          • 9.2.3.7.1.4. Periodic boundary condition
        • 9.2.3.7.2. Boundary condition specification
      • 9.2.3.8. General cross section weighting
        • 9.2.3.8.1. Scattering cross section transfer matrix weighting
        • 9.2.3.8.2. Weighting of the collapsed fission spectrum, \(\chi\)
        • 9.2.3.8.3. Weighting of the number of neutrons per fission
        • 9.2.3.8.4. Weighting of (n,2n), (n,3n), and (n,4n) cross sections
        • 9.2.3.8.5. Calculation and weighting of transport cross sections
          • 9.2.3.8.5.1. Outscatter approximation (inconsistent method)
          • 9.2.3.8.5.2. Inscatter approximation (consistent method)
          • 9.2.3.8.5.3. Weighting function for transport cross section
      • 9.2.3.9. Array definition
        • 9.2.3.9.1. Array types
        • 9.2.3.9.2. Pin-power edits
        • 9.2.3.9.3. Fill operations
        • 9.2.3.9.4. Examples of array definitions
      • 9.2.3.10. Homogenization block
      • 9.2.3.11. Assembly discontinuity factors
      • 9.2.3.12. Flux planes
      • 9.2.3.13. Mixing table block
    • 9.2.4. Examples of Inputs
      • 9.2.4.1. Sample 1
      • 9.2.4.2. Sample 2
        • 9.2.4.2.1. Sample 3
      • 9.2.4.3. Sample 4
      • 9.2.4.4. Sample 5
    • 9.2.5. Description of Output
      • 9.2.5.1. NEWT banner
      • 9.2.5.2. Input summary
        • 9.2.5.2.1. Control options
        • 9.2.5.2.2. Output options
        • 9.2.5.2.3. Input/output unit assignments
        • 9.2.5.2.4. Convergence control parameters
        • 9.2.5.2.5. Pin-power edit requests
        • 9.2.5.2.6. Geometry specifications
        • 9.2.5.2.7. Homogenization region specifications
        • 9.2.5.2.8. Material specifications
        • 9.2.5.2.9. Derived parameters
        • 9.2.5.2.10. Energy group structure listing
        • 9.2.5.2.11. Quadrature parameters
        • 9.2.5.2.12. Mixture volumes listing
        • 9.2.5.2.13. Mixing table listing
        • 9.2.5.2.14. Nuclide cross sections
        • 9.2.5.2.15. Mixture cross sections
      • 9.2.5.3. Iteration history
      • 9.2.5.4. Four-factor formula
      • 9.2.5.5. Fine-group balance tables
      • 9.2.5.6. Planar fluxes and currents
      • 9.2.5.7. Pin-power edits
      • 9.2.5.8. Broad-group collapse
        • 9.2.5.8.1. Broad-group summary data
        • 9.2.5.8.2. Broad-group cross section data
      • 9.2.5.9. Critical spectrum edit
      • 9.2.5.10. Assembly discontinuity factors
      • 9.2.5.11. Groupwise form factors
        • 9.2.5.11.1. Homogenized cross sections
      • 9.2.5.12. End-of-calculation banner
        • 9.2.5.12.1. Postscript graphics files
      • 9.2.5.13. Media zone edits
• 10. SCALE Nuclear Data Libraries
  • 10.1. SCALE Cross Section Libraries
    • 10.1.1. Introduction
    • 10.1.2. Description of the SCALE Cross Section Libraries
      • 10.1.2.1. The 238-group and 252-group ENDF/B-VII libraries (V7-238, v7-252)
        • 10.1.2.1.1. Differences in the 238-group and 252-group libraries
      • 10.1.2.2. The 56-group library
      • 10.1.2.3. The test-8grp library for code testing
      • 10.1.2.4. The 200N-47G (V7-200N47G) library for shielding
      • 10.1.2.5. The 28N-19G shielding libraries (V7.1-28N19G)
      • 10.1.2.6. The continuous-energy libraries
      • 10.1.2.7. Gleaning Data from the Multigroup Libraries
    • 10.1.3. Appendices
      • 10.1.3.1. MT Reaction Types on SCALE Cross-Section Libraries
  • 10.2. ORIGEN data resources
    • 10.2.1. Acknowledgements
    • 10.2.2. Version Information
      • 10.2.2.1. Version 6.3 (2021)
      • 10.2.2.2. Version 6.2 (2016)
      • 10.2.2.3. Version 6.1.3 (2011)
    • 10.2.3. Introduction
    • 10.2.4. Decay Resource
    • 10.2.5. Neutron Reaction Resource
    • 10.2.6. Fission Yield Resource
    • 10.2.7. Energy Resource
    • 10.2.8. Emission Resources
      • 10.2.8.1. Gamma Emission
      • 10.2.8.2. Neutron Emission
      • 10.2.8.3. Beta Emission
      • 10.2.8.4. Alpha Emission
    • 10.2.9. Decay Resource Format
    • 10.2.10. Fission Yield Resource Format
    • 10.2.11. Gamma Resource Format
    • 10.2.12. ORIGEN "end7dec" nuclide set
    • 10.2.13. Decay Resource Contents
    • 10.2.14. Reaction Resource Contents
  • 10.3. SCALE Nuclear Data Covariance Library
    • 10.3.1. Introduction
    • 10.3.2. Covariance Data Description
      • 10.3.2.1. Evaluated covariances from nuclear data files
      • 10.3.2.2. Approximate covariance data
      • 10.3.2.3. Modifications to covariance data
      • 10.3.2.4. Covariance data for fission spectra
    • 10.3.3. Multigroup Covariance Processing
    • 10.3.4. Contents of the SCALE 6.3 Covariance Library
    • 10.3.5. SCALE 6.1 44-group covariance library
• 11. Utility Modules for SCALE Libraries
  • 11.1. AMPX Library Utility Modules
    • 11.1.1. Introduction
    • 11.1.2. AJAX: MODULE TO MERGE, COLLECT, ASSEMBLE, REORDER, JOIN, AND/OR COPY SELECTED DATA FROM AMPX MASTER LIBRARIES
    • 11.1.3. ALPO: MODULE TO CONVERT AMPX LIBRARIES INTO ANISN FORMAT
    • 11.1.4. CADILLAC: MODULE TO MERGE MULTIPLE COVARIANCE DATA FILES
    • 11.1.5. COGNAC: MODULE TO CONVERT COVARIANCE DATA FILES IN COVERX FORMAT
    • 11.1.6. LAVA: MODULE TO MAKE AN AMPX WORKING LIBRARY FROM AN ANISN LIBRARY
    • 11.1.7. MALOCS: MODULE TO COLLAPSE AMPX MASTER CROSS-SECTION LIBRARIES
    • 11.1.8. PALEALE: MODULE TO LIST INFORMATION FROM AMPX LIBRARIES
    • 11.1.9. RADE: MODULE TO CHECK AMPX CROSS-SECTION LIBRARIES
    • 11.1.10. TOC: MODULE TO PRINT AN AMPX LIBRARY TABLE OF CONTENTS
  • 11.2. WORKER: SCALE System Module for Creating and Modifying Working-Format Libraries
    • 11.2.1. Introduction
    • 11.2.2. AMPX Library Format Conversion
    • 11.2.3. WORKER Input Specifications
      • 11.2.3.1. Input parameters
      • 11.2.3.2. Abbreviated input description
      • 11.2.3.3. Input/output assignments
    • 11.2.4. Sample Problem
      • 11.2.4.1. Sample problem input
      • 11.2.4.2. Reference
  • 11.3. COMPOZ Data Guide
    • 11.3.1. Introduction
    • 11.3.2. Input Data Description
      • 11.3.2.1. COMPOZ mode selector
      • 11.3.2.2. Library heading information
      • 11.3.2.3. Standard composition table
      • 11.3.2.4. Nuclide information table
      • 11.3.2.5. Isotopic distribution table
    • 11.3.3. Sample Problem
  • 11.4. ICE: Module to Mix Multigroup Cross Sections
    • 11.4.1. Introduction
    • 11.4.2. Cross Section Mixing Expressions
      • 11.4.2.1. Cross-section mixing for AMPX libraries
    • 11.4.3. Input Instructions
    • 11.4.4. Sample Problem
      • 11.4.4.1. Reference
  • 11.5. FIDO Input System
    • 11.5.1. Introduction
    • 11.5.2. Fixed-Field Input
    • 11.5.3. Free-Field Input
    • 11.5.4. User-Field Input
    • 11.5.5. Character Input
  • 11.6. MALOCS2: Module To Collapse AMPX Master Cross Section libraries
    • 11.6.1. Introduction
    • 11.6.2. MALOCS Input Data
    • 11.6.3. MALOCS Example Problem
• 12. Installing and Building SCALE
  • 12.1. System Requirements
    • 12.1.1. Supported Operating Systems
    • 12.1.2. Disk Space Requirements
    • 12.1.3. Memory
    • 12.1.4. Java requirements
  • 12.2. Installation Instructions
    • 12.2.1. SCALE 6.3 Data
  • 12.3. Running SCALE
    • 12.3.1. Running SCALE from Fulcrum
      • 12.3.1.1. Windows
      • 12.3.1.2. Linux
      • 12.3.1.3. Mac OS X
    • 12.3.2. Running SCALE from the Command Line
      • 12.3.2.1. Windows
      • 12.3.2.2. Linux
      • 12.3.2.3. Mac
    • 12.3.3. Example Invocation
    • 12.3.4. SCALE Variables
    • 12.3.5. Parallel Execution Capability
  • 12.4. SCALE Sample Problems
  • 12.5. Build Instructions
    • 12.5.1. Overview
    • 12.5.2. Required Resources
    • 12.5.3. Mac OSX Resources
  • 12.6. CMake Configuration
    • 12.6.1. Recommended Configuration Procedure
  • 12.7. Linux and Mac Configuration
    • 12.7.1. Windows Configuration
    • 12.7.2. Compilation
    • 12.7.3. Compilation Flags
    • 12.7.4. Installation