Insights Blog
-- Browse All Articles --
Physics Articles
Physics Tutorials
Physics Guides
Physics FAQ
Math Articles
Math Tutorials
Math Guides
Math FAQ
Education Articles
Education Guides
Bio/Chem Articles
Technology Guides
Computer Science Tutorials
Forums
General Engineering
Mechanical Engineering
Electrical Engineering
Aerospace Engineering
Nuclear Engineering
Materials Engineering
Trending
Featured Threads
Log in
Register
What's new
Search
Search
Search titles only
By:
General Engineering
Mechanical Engineering
Electrical Engineering
Aerospace Engineering
Nuclear Engineering
Materials Engineering
Menu
Log in
Register
Navigation
More options
Contact us
Close Menu
JavaScript is disabled. For a better experience, please enable JavaScript in your browser before proceeding.
You are using an out of date browser. It may not display this or other websites correctly.
You should upgrade or use an
alternative browser
.
Forums
Engineering
Nuclear Engineering
MCNP6.2 - ENDF/B reaction numbers for tally multiplier
Reply to thread
Message
[QUOTE="Alex A, post: 6900979, member: 690804"] This has more the feeling of a corrupt input file causing mcnp to explode than an install issue for me. I really don't know 6 that well though. Do check what is being suggested, but if you can share your input file could you rename it to add .txt and attach it to a post please? [/QUOTE]
Insert quotes…
Post reply
Forums
Engineering
Nuclear Engineering
MCNP6.2 - ENDF/B reaction numbers for tally multiplier
Back
Top