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CCC-0732 SCALE5.1/ORIGEN. (Abstract last modified 06-MAR-2008)
1.
NAME OR DESIGNATION OF PROGRAM - SCALE 5.1/ORIGEN. The package contains SCALE 5.1 and ORIGEN-ARP 5.1. 2.
COMPUTER FOR WHICH THIS PACKAGE IS DESIGNED -
To request or retrieve programs click on the one of the active versions below.
A password and special authorization is required. Explanation of the status codes.
Machines used:
Package-ID Orig.Computer Test Computer
CCC-0732/03 POWER MAC,Linux-based PC,PC Windows,UNIX gen. W.S.
3.
DESCRIPTION OF PROGRAM OR FUNCTION - The SCALE system was developed for the Nuclear Regulatory Commission to satisfy a need for a standardized method of analysis for the evaluation of nuclear fuel facility and package designs. In its present form, the system has the capability to perform criticality, shielding, radiation source term, spent fuel depletion/decay, and reactor physics analyses using well-established functional modules tailored to the SCALE system. See the developers' website and the SCALE 5 electronic notebook for news on SCALE, updates, and tips on running the code. 4.
METHODS - The SCALE system consists of easy-to-use analytical sequences which are automated to perform the necessary data processing and manipulation of well-established computer codes required by the sequence. Thus the user is able to select an analytical sequence characterized by the type of analysis (criticality, shielding, or heat transfer) to be performed and the geometric complexity of the system being analyzed. The user then prepares a single set of input for the control module corresponding to this analytical sequence. The control module input is in terms of easily visualized engineering parameters specified in a simplified, free-form format. The control modules use this information to derive additional parameters and prepare the input for each of the functional modules in the analytical sequence. Provisions have also been made to allow the user to execute the functional modules on a stand-alone basis. The radiation transport codes employ either discrete-ordinates or Monte Carlo methods. 5.
RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM - Modeling assumptions that limit or restrict the usefulness or accuracy of the individual module are discussed in the documentation. 6.
TYPICAL RUNNING TIME - Runtimes for sample problems vary from approximately 8 hours to 24 hours depending on the speed of the machine. Running times are extremely problem dependent and depend heavily on the sequence used and the cross-section library selected. They range from less than one minute for a simple 1-D criticality or depletion/decay problem to several hours for a 3-D complex sensitivity/uncertainty analysis or 3-D Monte Carlo depletion case. 9.
STATUS 10.
REFERENCES - 11.
HARDWARE REQUIREMENTS - 12.
PROGRAMMING LANGUAGE -CCC-0732/03: C-LANGUAGE FORTRAN-90 FORTRAN-95 13.
SOFTWARE REQUIREMENTS - 15.
NAME AND ESTABLISHMENT OF AUTHORS - 16.
MATERIAL AVAILABLE -CCC-0732/03: 17.
CATEGORIES - Keywords: BURNUP, CALCULATIONS, COMPLEX GEOMETRY, CONTINUOUS ENERGY, CRITICALITY, CROSS SECTIONS, DEPLETION, DISCRETE ORDINATES, DOSE, GAMMA RAY SOURCE, ISOTOPE INVENTORY, MONTE CARLO METHOD, MULTIGROUP, NEUTRON, PLOTTING, SENSITIVITY ANALYSIS, SPENT FUEL CHARACTERISATION, UNCERTAINTY ANALYSIS
Program-name Package-ID Status
SCALE5.1/ORIGEN CCC-0732/01 Obsolete
SCALE5.1/ORIGEN CCC-0732/03 Arrived
SCALE newsletter: http://www.ornl.gov/sci/scale/newsletter.htm
What's New in SCALE5.1? http://rsicc.ornl.gov/rsiccnew/SCALE5.1_WhatsNew.pdf
SCALE website http://www.ornl.gov/sci/scale
electronic notebook: http://rsicc.ornl.gov/rsiccnew/CFDOCS/scale5enotebook.cfm
The CSAS control module contains criticality safety analysis sequences that calculate the neutron multiplication factor for one-dimensional (XSDRNPM-S) and multidimensional (KENO V.a) system models. The CSAS module also has the capability to perform criticality searches (optimum, minimum, or specified values of k-eff) on geometry dimensions or nuclide concentrations in KENO V.a. The CSAS6 control module contains criticality safety analysis sequences using the KENO-VI module for multidimensional models with more complex geometries, including hexagonal arrays. Sequences that provide problem-dependent cross sections for use in stand-alone codes are also available in the CSAS module.
In addition, sensitivity and uncertainty (S/U) analysis capabilities for criticality safety are included in SCALE 5.1. Both 1-D and 3-D sequences plus several auxiliary codes have been developed into a new suite of sensitivity and uncertainty analysis codes called TSUNAMI (Tools for Sensitivity and Uncertainty Analysis Methodology Implementation). TSUNAMI contains a number of codes that were developed primarily to assess the degree of applicability of benchmark experiments for use in criticality code validations. However, the sensitivity and uncertainty data produced by these codes can be used in a wide range of studies. Sensitivity coefficients produced by the TSUNAMI sensitivity analysis sequences predict the relative changes in a system's calculated k-eff value due to changes in the neutron cross-section data. Both TSUNAMI-1D and TSUNAMI-3D fold the sensitivity data with cross-section covariance data to calculate the uncertainty in the calculated k-eff value due to tabulated uncertainties in the cross-section data. The applicability of benchmark experiments to the criticality safety validation of a given application can be assessed using S/U-based integral indices. The TSUNAMI-IP (Indices and Parameters) code utilizes sensitivity data and cross-section covariance data to produce a number of relational integral indices that can be used to assess system similarity.
The SAS2H module uses ORIGEN-S to perform a one-dimensional (1-D) fuel depletion analysis (to characterize spent fuel and/or generate source terms).
Two-dimensional (2-D) spent fuel depletion is available in the TRITON control module. TRITON couples ORIGEN-S depletion calculations with the 2-D flexible mesh discrete ordinates code NEWT. TRITON supports branch calculations that allow calculation of cross sections and their first derivatives with respect to fuel and moderator temperature, moderator density, soluble boron concentration, and control rod insertion, as a function of burnup. These cross sections are stored in a database format that can be retrieved and processed as appropriate for use by core analysis codes. The rigor of the NEWT solution in estimating angular flux distributions combined with the world-recognized accuracy of ORIGEN-S depletion gives TRITON the capability to perform rigorous burnup-dependent physics calculations with few implicit approximations.
Three-dimensional (3-D) Monte Carlo spent fuel depletion is a new capability added in SCALE 5.1 via the TRITON and TRITON6 control modules. TRITON couples ORIGEN-S depletion calculations with KENO V.a, while TRITON6 uses KENO-VI.
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ORIGEN-ARP is an automated depletion decay sequence for both Windows and Unix/Linux systems. It includes a Windows graphical user interface (GUI) for ORIGEN-S and ARP (Automated Rapid Processing), which automatically interpolates cross sections on enrichment, burnup, and optionally moderator density using a set of standard basic cross-section libraries for LWR and MOX fuel assembly designs. The interpolated cross sections are passed to ORIGEN-S. Utility codes are provided so users can generate their own ORIGEN-ARP basic cross-section libraries via TRITON or SAS2H.
Other automated criticality safety related sequences include the STARBUCS 3-D burnup credit sequence (combining ORIGEN-ARP with KENO V.a or KENO-VI) and the SMORES 1-D material optimization sequence for criticality safety.
Four shielding analysis sequences are provided. SAS1 analyzes general one-dimensional shielding problems via XSDRNPM-S. SAS3 provides a general procedure for cross-section preparation followed by a shielding analysis using the MORSE-SGC Monte Carlo code. The SAS4 module has been tailored to perform a Monte Carlo shielding analysis for a cask-type geometry. An automated scheme is incorporated in SAS4 to generate Monte Carlo biasing parameters that enable SAS4 to calculate accurate doses with reasonable efficiency. The QADS module analyzes three-dimensional gamma-ray shielding problems via the point kernel code, QAD-CGGP.
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DATA LIBRARIES INCLUDED:
SCALE Standard Composition Library
16 group criticality cross sections from Hansen Roach
44 group cross sections based on ENDF/B V
238 group cross sections based on ENDF/B V
238 group cross sections based on ENDF/B VI
27n, 18g coupled cross sections based on ENDF/B IV
22n, 18g coupled cross sections based on Straker Morrison
18 group photon cross sections based on OGRE data
ENDF/B-V continuous energy cross sections for CENTRM
ENDF/B-VI continuous energy cross sections for CENTRM
Albedos and weighting functions for use by KENO
Various cross section, decay, and yield libraries for ORIGEN S
ORIGEN ARP basic cross section libraries:
- Siemens 14x14
- Westinghouse CE 14x14, 16x16
- Westinghouse 14x14, 15x15, 17x17, 17x17 OFA (Optimized Fuel Assembly)
- GE 7x7, 8x8, 9x9, 10x10
- ABB 8x8
- ATRIUM-9 (9x9), ATRIUM-10 (10x10)
- SVEA-64 (8x8), SVEA-100 (10x10)
- VVER-440 flat enrichment (1.6% - 3.6%)
- VVER-440 profiled enrichment, average 3.82%
- VVER-440 profiled enrichment, average 4.25%
- VVER-440 profiled enrichment, average 4.38%
- VVER-1000
- CANDU 28- and 37-element bundles (available also in DLC-0210)
- AGR (Advanced Gas Cooled Reactor)
- Magnox
- Mixed oxide (MOX) fuel: 8x8, 9x9-1, 9x9-9, 10x10, 14x14, 15x15, 16x16, 17x17, 18x18
CCC-0732/03:
The Windows version was updated in August 2007 for compatibility with Vista.
CCC-0732/01: 06-MAR-2008 Obsolete
CCC-0732/03: 06-MAR-2008 Masterfiled Arrived
Background reference:
- B.D. Murphy:
ORIGEN-ARP Cross-Section Libraries for the RBMK-1000 System (ORNL-TM-2006/139, November 2006)
CCC-0732/03:
- Excerpts from SCALE Newsletter, January 2005 and July 2006
(Whats New in SCALE5.1.pdf).
- 'Getting Started with SCALE 5.1 for Windows'
(GettingStarted.pdf, November 2006, revised August 2007).
- README for SCALE 5.1 on Unix, Linux, and Mac
(README_5.1_Unix_Linux_Mac.pdf, November 2006).
- SCALE: A Modular Code System for Performing Standardized Computer Analyses
for Licensing Evaluations, ORNL/TM-2005/39, Version 5.1, Vols. I-III, Nov.2006.
The UNIX version of SCALE was fully tested on HP/Compaq Alpha, Linux, and Intel Mac OSX. It was also built on SunOS, IBM RS/6000, and HP workstations although these systems had old compilers and insufficient memory to run all the sample cases. It requires approximately 5 GB of disk space to create executables and data libraries and run sample problems. A minimum of 1 GB RAM is required, and more may be needed for large problems.
The Windows version runs on Pentium personal computers with a minimum of 512 MB RAM (1 GB recommended). Nominal hard disk requirements are 5 GB for a complete installation, including space for running sample problems. SCALE runs on Windows XP or Windows VISTA.
Executables included in the Windows package were created using the Lahey F95 Fortran compiler version 7.1 on a 32-bit Pentium 4 under Windows XP. In August 2007, the package was updated to provide compatibility with the new Windows Vista operating system. Makefiles, source files, data libraries, and batch files are included in the package.
Fortran 95 and C compilers are required to build the Unix version. The Unix DVD includes Linux executables compiled with Intel ifort version 9.1.039 on an AMD Opteron running the RedHat Enterprise Linux 4 and Intel Mac OSX executables created with Intel ifort compiler 9.1. All distributed binaries are 32-bit. No other executables are included for Unix or Linux because of incompatibilities in runtime libraries. Scripts and makefile flags allow the source code to compile on HP/Compaq Alpha OSF/1, Linux PC, Intel Mac OSX, IBM/AIX, HP/HP_UX11 and SUN/Solaris. Note that the HP, Sun, and IBM systems on which it was tested are older systems with compilers that do not fully support some newer Fortran standards that are included in SCALE 5.1. As a result, some errors were encountered on these systems. If you encounter problems compiling or running on these systems, please check the SCALE 5 Notebook for guidance and possible updates. Note that makefiles are included for creating executables, installing libraries and running sample problems on Unix and Linux. Binary (big endian format) AMPX master libraries are included in this distribution. The 'little endian' machines are able to read 'big endian' ordered files using options specified in the cmds/scale5 script that set necessary environmental variables for this to happen.
SCALE 5.1 runs in serial mode; there is no parallel version. This version was developed using Compaq Fortran 90 V5.5A on a DEC Alpha 500/500 workstation under Tru64 V5.0. SCALE 5.1 was tested on the following systems.
- DEC6600 running Tru64 Unix V5.0A, Tru64 Unix V5.1A with HP Fortran V5.5A and C compiler V6.1 and V6.4
- DEC6600, DEC4100, and other DEC's running Digital Unix V4.0D, V4.0F, V4.0D with Compaq Fortran V5.5 and DEC C V5.9
- Intel Xeon running Fedora Core 5 with Intel Fortran 95 version 9.1 and GNU gcc 4.1.1
- AMD Opteron running RedHat Enterprise Linux 4 with Intel ifort version 9.1.039 and gcc 3.4.6
- Intel Mac OS X with Intel 9.1
- Sun SPARCstation-20 running Solaris 5.7 with Fortran 95 8.2 and C 5.8
- IBM RS/6000 590 running AIX 5.1 with XL Fortran 08.01.0000.0003 and C 5.0.0.0
- HP workstation running HP-UX B.11.11, Fortran HP F90 2.9, C/HP-UX B.11.11.12
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SCALE5.1 updates are available from the developers'website: http://www.ornl.gov/sci/scale/scale_5_1_updates.htm
Contributed by:
Radiation Shielding Information Center
Oak Ridge National Laboratory
Oak Ridge, Tennessee, U. S. A.
Developed by: Oak Ridge National Laboratory
Oak Ridge, Tennessee, U. S. A.
- Unix/Linux version: source codes, Linux executables, Intel Mac OSX
executables, binary data libraries, makefiles, scripts, and sample problem input
and output
- Windows version: source codes, executables, binary data libraries, makefiles,
batch files, and sample problem input and output
- B. Spectrum Calculations, Generation of Group Constants and Cell Problems
- C. Static Design Studies
- D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics
- G. Radiological Safety, Hazard and Accident Analysis
- H. Heat Transfer and Fluid Flow
- J. Gamma Heating and Shield Design
- K. Reactor Systems Analysis
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