MCNP6 BURN -- Testing about burnable poison depletion

In summary, the conversation discusses using mcnp6 for burnable poison depletion calculations. The initial fuel composition is given as m1 with uranium and oxygen isotopes, and m12 with gadolinium and oxygen isotopes for the burnable poison. However, this caused a fatal error and the user had to use the omit option to exclude certain nuclides that use physics models instead of data tables. The conversation then mentions the possibility of turning on advanced physics or installing ENDF-VIII to see if it has data for the gadolinium isotopes.
  • #1
goyu96
1
0
Hello, I'm testing about burnable poison depletion with mcnp6.

I'm using
m1 92233.82c -7.91619E-01
90232.82c -8.75802E-02
8016.82c -1.20800E-01
for fuel

and
m12 64152.82c -1.39023E-03 $ gd-152
64154.82c -1.53529E-02 $ gd-154
64155.82c -2.39616E-01 $ gd-155
64156.82c -1.46035E-01 $ gd-156
64157.82c -2.56647E-01 $ gd-157
64158.82c -1.79482E-01 $ gd-158
64160.82c -1.59950E-01 $ gd-160
8016.82c -1.52669E-03 $ o-16
for burnable poison.
but this caused fatal error
-----
The following nuclides use physics models rather than data tables:

6014. c
7016. c
8018. c
9018. c
64151. c
64159. c
66157. c
66159. c
------
so I used omit option
omit= -1 8 6014 7016 8018 9018 64151 64159 66157 66159
Then It works, but, I want calculate gadolinia (64151, 64159)..
how can I do this?
 
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  • #2
Have you tried turning the advanced physics on instead of using the omit line? You could check the decay products Tb-151 and Eu-159 are being produced.

It might be fine as it is. Unless the capture cross section is huge it might not affect the answer much.

Another option might be to install ENDF-VIII and see if it has data for those isotopes.
 

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