Hi All,
I’m using openmc to get a multigroup hexagonal(5 ring) problem with reflective boundary condition.
the geometry is a sixth symmetry, the plotted figure is attached.

my problem is that the keff and flux distribution from openmc is far away from reference. is there any restriction for openmc to model the kind of geometry or some options needed to be open?

I think your boundary conditions has some problems.

Transmission boundary between assemblies

Vacuum boundary outside of the geometry &

Periodic boundary condition should be used in the two planes which is covering your 1/6 th portion of the geometry.

Also, if the geometry is infinite in z-axis you can use to planes in z-axis to bind it with reflective boundary conditions. About the vacuum boundary condition, it depends on your geometry. If it is infinite without any leakage then you should use reflective boundary condition instead of vacuum boundary as mentioned in point 2 above.

I found the reasion is that I used complicated surface for the bottom of the geometry, geometry.xml input is given at the end.

the openmc runs well when I change the bottom surface to a y-plane, but this boundary is not what i need for my benchmark problem. by the way, my benchmark problem is simple 5 rings hexagonal problem with pin pitch sqrt(3.0), the boundary condition for all outer surface is reflective.

then my question is how to model the benchmark problem?

thank you very much.

Li,ZY

I changed the geometry to this, then OpenMC can run well.

Sorry to say but i didn’t understand your problem yet. Your geometry has five rings with a pitch of sqrt (3). So is it an assembly? Or a core? & what is the problem you are facing modeling it?

If it’s simply about modeling then the given examples are already enough for you i guess

the problem is a simple 5-ring min-assembly problem. the inner 4 rings are fuel pins and the outer ring is moderator pins. the figure is attached. and the outer boundary conditon is reflective.

this problem is diffrent from the example because there is a large hexagon with boundary conditon to be filled with hex_lattice in example. so my question is how to model this 5-ring hex_lattice only?

Follow the example, create two universes one for fuel & another with moderator (outer universe). start from ring 5 instead of ring 7 & this will give you an assembly with 5 rings. Place the universes according to your model description. Give lattice pitch sqrt (3) instead of 1.275. Put the value for edge length of the assembly according to your assembly pitch.

Sorry to say that my problem is a multi-pin problem (61 pins in total) WITHOUT assembly edge, so that my boundary is the outest pins’ out side. this problem is defined not similar to real hexagonal assembly in order to test hexagonal deterministic method (e.g. Hexagonal Sn method or SP3 method).

the forum system just allow me to upload xml file, so the XS python file and geometry.xml and materials.xml file are attached. the Reference keff of this problem (without Gd) is about 1.2183. cuurently I can’t accurately incorperate reflective boundary condition as I want, so the result from OpenMC is 1.1797, this value is equal to the result for all the pins being fuel only; I guess this is because the boundary conditon setted in my geometry.xml bypass the outest ring of water pins.

Hi All,
could developer kindly reply if OpenMC can model this simple problem?
It is just a 7-pin hexagonal problem with reflective outer boundary conditon, the difficulty for me is how to model it WITHOUT “assembly edge”.
Thanks you very much.
I just want to use it as a benchmark result for my deterministic code developed.