Send e-mail to email@example.com
Unix CPU Hosts:
For access to servers and cluster computing, please send e-mail to firstname.lastname@example.org
To use NE/RHP software on the NE/RHP Servers or Engineering / EECS High Performance Computing Cluster
(Add the following to the .cshrc file)
To use the Engineering / EECS High Performance Computing Cluster
(Add the following to the .cshrc file)
MCNP/SCALE is export controled. You must gain approval from RSICC.
Before you can get or use MCNP/SCALE you must first become a registered user.
After you have registered you can order MCNP online at http://www-rsicc.ornl.gov/rsiccnew/CFDOCS/REQUEST_FORM.cfm, or you can fax or mail in the pdf software request
RSICC will send an e-mail indicating they have approved your request and are sending the MCNP package. You can forward this conformation e-mail to Support and they will add you to the valid user list for the NE/RHP servers.
MCNP and SCALE is available on the NE/RHP CPU servers and Engineering / EECS High Performance Computing Cluster.
To run MCNP/SCALE a working input deck must be put in the directory where the output files are to be saved. The deck can be created by hand ( for creation of MCNP/SCALE decks please see the MCNP/SCALE manual ) or supplied.
Next to run the deck issue this command:
mcnp5 inputFileName outputFileName
One issue when running from off campus is that SSH connections may be disconnected. To avoide this place 'nohup' in front of the command.
To terminate a running process type in 'ps -aux | grep user_name'. This will list all process with that user name and provide the PID of the MCNP/SCALE process. Next type 'kill [PID]' and that should terminiate the process.
A script file is a file which contains a list of commands for a server to complete. Scripts are standard unicode text files that are saved with no dot extensions. (this means they are not saved as *.txt or *.doc ) . More information on writting scripts can be found at Using the Engineering / EECS High Performance Computing Cluster webpage.
|You can use whatever text editor you wish to create your input file. However, there are a few properties the file must have in order for it to work with MCNP/SCALE. First, it needs to be saved in unicode format. This means it shouldn't be followed by a .txt or .doc extension. The second is that it must be in unix format. If you create the file in windows it will be created in dos format (This has a different invisible return character that isn't recognized by MCNP). To convert from dos to unix or vise versa you can use the following commands on the servers.
If you have a Mac or Unix machines this will automatically save the file in the correct format (remember there still should not be any extensions on it ie. .txt).
As far as editing or creating files directly on the servers you can use the program pico, nedit or emacs. These are all unix editors that are pretty simple to use.
These are not your only options there are other unix editors and some windows editors have conversion functions built in. ( A common one is Edit Pad Lite. )
Note that earlier versions of MCNP do no recognize the tab character. The most recent versions fix this, but keep this in mind if your input deck fails; the use of tabs could be the culprit.
The department has access to the following Thermal Hydraulic and Reactor System Analysis codes. Please see Dr. Brian Woods (email@example.com) to gain access to these codes.
The TRAC/RELAP Advanced Computational Engine. A modernized thermal-hydraulics code designed to consolidate the capabilities of NRC's 3 legacy safety codes - TRAC-P, TRAC-B and RELAP. It is able to analyze large/small break LOCAs and system transients in both PWRs and BWRs. The capability also exists to model thermal hydraulic phenomena in both 1-D and 3-D space. This is NRC's flagship thermal-hydraulics analysis tool.
Small break LOCA and system transient analysis tool for PWRs or BWRs. It has the capability to model thermal hydraulic phenomena in 1-D components.
RELAP5-3D is the latest in the RELAP5 code series developed at the Idaho National Laboratory (INL) for the analysis of transients and accidents in water-cooled nuclear power plants and related systems as well as the analysis of advanced reactor designs. The RELAP5-3D code is an outgrowth of the one-dimensional RELAP5/MOD3 code developed at the INL. The most prominent attribute that distinguishes RELAP5-3D© from its predecessors is the fully integrated, multi-dimensional thermal-hydraulic and kinetic modeling capability. (http://www.inl.gov/relap5/)
Symbolic Nuclear Analysis Package, SNAP, is a graphical user environment designed to assist the NRC code user in all aspects of input model development. This involves such tasks as the 1) the actual development of code input decks, 2) executing the models that have been developed, 3) visualizing the code output, and 4) managing the history of new and old legacy models alike.
MELCOR is a fully integrated, engineering-level computer code that models the progression of severe accidents in light-water reactor nuclear power plants. (http://melcor.sandia.gov/)
VIPRE (Versatile Internals and Component Program for Reactors; EPRI) is used for nuclear reactor thermal-hydraulic analysis applications. It was designed to help evaluate nuclear reactor core safety limits including minimum departure from nucleate boiling ratio (MDNBR), critical power ratio (CPR), fuel and clad temperatures, and coolant state in normal operation and assumed accident conditions.
GOTHIC is most widely known for its uses in containment analysis. However, large bubble flow through pipes, Hydrogen burns, suppression pools and water hammers are all areas in which GOTHIC excels. (http://www.numerical.com/gothic/gothic_main.htm)
General computational fluid dynamics solver. (http://www.cd-adapco.com/products/STAR-CCM_plus/index.html)
If you have any questions please send email to firstname.lastname@example.org