SCALE Software Coordinator
This topic has been migrated from the SCALE 5 ORIGEN notebook.
Date: Mon Jan 5 15:27:18 2009
So I would like ask you if you can help me.
I need help with burnup calculations in origen arp 5.1. I am solving diploma project and I have MCNP model of VVER440 fuel assembly 3.82% and I need fill it up with fuel material. I know how to prepare input file, but I would like ask if i am not doing some mistakes.
I would like calculate isotopic composition afer 20000, 25000 or 30000 MWd/tHM. What is necessary put to the input file to obtain real results? I have only these information about campaigns for 3.82%:
1. irradiation 300 days
2. outage - decay 40 days
3. irradiation 300 days
4. outage - decay 40 days
5. irradiation 300 days
6. outage - decay 70 days
7. irradiation 300 days
Or, do I need configure or edit some libraries???
I will be very grateful, if you send me some tips :)
Respectfully yours, Tomas Melo.
SCALE Software Coordinator
Dear Tomas
You do not need to reconfigure or change any libraries. The existing libraries for VVER 440 have been extensively tested and validated, and developed for 3.82% enrichment. I would highly recommend using the Windows graphical interface to create the input and solve the problem. It will guide you through required input and also allow you to convert the isotopic compositions to the units required for MCNP transport calculations. Note that we have performed a number of VVER validation studies using the distributed libraries that can be obtained from the SCALE publications website http://scale.ornl.gov/publications.shtml
If you have specific problems or questions about the input don't hesitate to contact us.
Sincerely
Ian Gauld
ORIGEN Code Manager