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.
 

Related to MCNP6 BURN -- Testing about burnable poison depletion

What is MCNP6 BURN used for?

MCNP6 BURN is used for simulating the depletion of burnable poisons in nuclear reactors. It helps in understanding how materials that absorb neutrons (burnable poisons) change over time, which is crucial for reactor safety and efficiency.

How does MCNP6 BURN handle burnable poison depletion?

MCNP6 BURN uses coupled neutron transport and depletion calculations. It models the interaction of neutrons with materials and tracks the changes in composition of burnable poisons as they absorb neutrons and transmute into other isotopes.

What are the common burnable poisons modeled in MCNP6 BURN?

Common burnable poisons include materials like boron-10, gadolinium-157, and samarium-149. These materials are chosen because of their high neutron absorption cross-sections, which make them effective in controlling the reactivity of a reactor.

Can MCNP6 BURN simulate long-term reactor operation?

Yes, MCNP6 BURN can simulate long-term reactor operation by performing time-dependent calculations. It allows users to model the depletion and buildup of isotopes over extended periods, providing insights into the behavior of burnable poisons throughout the reactor's lifecycle.

What are the input requirements for MCNP6 BURN simulations?

MCNP6 BURN simulations require detailed input data, including the geometry of the reactor, material compositions, neutron source information, and specific burnable poison characteristics. Accurate input data is essential for reliable simulation results.

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