The difference flux between openMC and MCNP(MCX)

Validation and Verification
1

hi,nowadays I try to use openMC to calculate the flux about BSA in BNCT
openMC flux=20.3288
MCNP flux=44.667
MCX(a MC program developped by XJTU) flux=45.13
I dont know how to solve it

2

I cant upload files，I really hope anyone can connect me by email：rbj810124130@gmail.com

3

after some test, a strange result appear：
if I change the energy in openMC from 1 to 1000，flux=45.5616

I try this energy with other different source position，and get the same conclusion: flux with 1000 times more energy in openMC can match the flux in mcnp

my code about source：
source = openmc.Source() source.space = openmc.stats.Point((0,0,0)) source.angle = openmc.stats.Isotropic() source.energy = openmc.stats.Discrete([1000.0], [1.0]) source.particle = 'neutron'