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lwr.py
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lwr.py
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#############################
### General specifcations ###
#############################
reactor = "lwr"
burn_regions = 1 # Number of burnup annular regions.
burn_time = 4200 # Number of days to burn the material [days]
time_step = 525 # Coarse Time step by which to increment the burn, for MCNP [days]
email = "[email protected]" # E-mail address to send job information to.
scheduler = "PBS"
number_cpus = 3 # Number of CPUs to run transport code on.
cpus_per_node = 4 # Processors per node
verbosity = 100
# Set isotopes to track
from char.iso_track import load, transmute
core_load_isos = load # Initial core loading nuclide list or file
core_transmute_isos = transmute # Transmutation tracking nuclide list or file
# Load stock template string from char
# Having this allows users to specify other templates
from char.templates.lwr import serpent
xs_gen_template = serpent.xs_gen
burnup_template = serpent.burnup
################################
### Unit Cell Sepcifications ###
################################
fuel_cell_radius = 0.410
void_cell_radius = 0.4185
clad_cell_radius = 0.475
unit_cell_pitch = 0.65635 * 2.0
unit_cell_height = 10.0
#fuel_density = [10.7, 10.7*0.9, 10.7*1.1] # Denisty of Fuel
fuel_density = [10.7*0.95, 10.7*1.05] # Denisty of Fuel
clad_density = 5.87 # Cladding Density
cool_density = 0.73 # Coolant Density
fuel_specific_power = 40.0 / 1000.0 # Power garnered from fuel [W / g]
###########################
### MCNPX Specification ###
###########################
# LEU
initial_heavy_metal = { # Initial heavy metal mass fraction distribution
922350: 0.04,
922380: 0.96,
}
#initial_U235 = [0.02, 0.04, 0.06]
initial_heavy_metal = { # Initial heavy metal mass fraction distribution
922340: 0.01,
922350: 0.04,
922380: 0.95,
}
#initial_U235 = [0.02, 0.04, 0.06]
initial_U235 = [0.03, 0.05]
#sensitivity_mass_fractions = [1.1, 0.9]
# UOX
fuel_chemical_form = { #Dictionary of initial fuel loading.
80160: 2.0,
"IHM": 1.0,
}
fuel_form_mass_weighted = True # Flag that determines if the fuel form should be mass weighted (True) or atom weighted (False)
k_particles = 5000 #Number of particles to run per kcode cycle
k_cycles = 130 #Number of kcode cycles to run
k_cycles_skip = 30 #Number of kcode cycles to run but not tally at the begining.
group_structure = [1.0e-09, 1.0e-08, 1.0e-07, 1.0e-06, 1.0e-05, 0.0001, 0.001, 0.01, 0.1, 1.0, 10.0]
# Temperature
# Should be a positive multiple of 300 K (ie 300, 600, 900, etc)
temperature = 600
###################################
### Remote Server Specification ###
###################################
remote_url = "nukestar.me.utexas.edu" #Remote server address
remote_user = "scopatz" #Remoter username
remote_dir = "/home/scopatz/" #Remote directory to store files.
remote_gateway = 'nukestar01'
RemotePathMPI = "/usr/local/bin/mpiexec" #Remote Path to 'mpirun'
RemotePathMCNP = "/usr/share/mcnpxv260/bin/mcnpx260" #Remote Path to mcnp
RemoteDATAPATH = "/usr/share/mcnpxv260/lib/" #Remote DATAPATH enviromental variable
#############################
### Serpent Specification ###
#############################
serpent_xsdata = "/usr/share/serpent/xsdata/endf7.xsdata" # Specifiy which XS library of serpent's to use.
#serpent_xsdata = "/usr/share/serpent/xsdata/jeff311.xsdata" # Specifiy which XS library of serpent's to use.
# The following two are only needed for burnup runs
serpent_decay_lib = "/usr/share/serpent/xsdata/sss_endfb7.dec" # Specifiy which decay library of serpent's to use.
serpent_fission_yield_lib = "/usr/share/serpent/xsdata/sss_endfb7.nfy" # Specifiy which decay library of serpent's to use.
#serpent_decay_lib = "/usr/share/serpent/xsdata/sss_jeff311.dec" # Specifiy which decay library of serpent's to use.
#serpent_fission_yield_lib = "/usr/share/serpent/xsdata/sss_jeff311.nfy" # Specifiy which decay library of serpent's to use.