MSCS for burnup calculations
Revision as of 14:18, 29 November 2017 by Antti Rintala (talk | contribs)
The Minimal Serpent Coupling Script (MSCS) for burnup calculations is a short (~ 400 lines with comments) Python program intended to give a minimal working example of a wrapper program that can communicate with Serpent in the coupled burnup calculation mode. MSCS provides a working example of externally coupled multi-physics simulations with Serpent and may be a good starting point for the users that are interested in running such simulations with Serpent.
Contents
Description
The coupling script communicates with Serpent using the file based communication mode.
Here, the coupling script calculates the fuel temperature solution itself using a not-very-physical functional expansion for fuel temperature as a function of power and local burnup. In many cases that part of the coupling script should be replaced by writing the input for an external solver, running the external solver and reading the results from the external solver output.
The temperature treatment of the interaction physics is done on-the-fly using the TMS temperature treatment technique for the base cross sections and interpolation of thermal scattering data for the thermal scattering libraries.
The problem solved here is a 200 cm long fuel rod in infinite lattice with axially black boundary conditions. The fuel rod is divided axially into 10 depletion zones, for which the fuel temperature is solved by MSCS.
One of the provided inputs uses the explicit Euler discretization for the depletion solution with stochastic approximation based relaxation applied to the tallied transmutation cross sections and one-group fluxes. The second input uses the Stochastic Implicit Euler's method[1].
Files
MSCS.py
#############################################################
# #
# Minimal Serpent Coupling Script v 0.2 #
# For burnup example #
# #
# Created by: Ville Valtavirta 2016/01/04 #
# Modified by: Ville Valtavirta 2016/01/05 #
# #
#############################################################
import os
import signal
import math
import time
# Path to Serpent executable
sssexe = '/home/vvvillehe/Serpent2/2.1.27/sss2'
#######################################################
# Create the Serpent input-file for this run #
# (process id or communication file must be appended) #
#######################################################
# Open original input for reading
file_in = open('./input','r')
# Open a new input file for writing
file_out = open('./coupledinput','w')
# Write original input to new file
for line in file_in:
file_out.write(line)
# Close original input file
file_in.close()
# Append signalling mode
file_out.write('\n')
file_out.write('set comfile com.in com.out\n')
# Append interface names
file_out.write('\n')
file_out.write('ifc cool.ifc\n\n')
file_out.write('ifc fuel.ifc\n')
# Close new input file
file_out.close()
##############################################
# Write the initial coolant interface file #
# (Coolant conditions will be held constant) #
##############################################
file_out = open('./cool.ifc','w')
# Write the header line (TYPE MAT OUT)
file_out.write('2 cool 1\n')
# Write the output line (OUTFILE NZ ZMIN ZMAX NR)
file_out.write('coolifc.out 10 -100 100 1\n')
# Write the mesh type
file_out.write('1\n')
# Write the mesh size (NX XMIN XMAX NY YMIN YMAX NZ ZMIN ZMAX)
file_out.write('1 -0.75 0.75 1 -0.75 0.75 1 -100 100\n')
# Write initial coolant temperatures and densities
for i in range(1):
file_out.write('-0.9 520.0\n')
# Close interface file
file_out.close()
##############################################
# Write the initial fuel interface file #
# (Fuel temperature will be updated) #
##############################################
file_out = open('./fuel.ifc','w')
# Write the header line (TYPE MAT OUT)
file_out.write('2 fuel 0\n')
# Write the mesh type
file_out.write('1\n')
# Write the mesh size (NX XMIN XMAX NY YMIN YMAX NZ ZMIN ZMAX)
file_out.write('1 -0.75 0.75 1 -0.75 0.75 10 -100 100\n')
# Write initial fuel temperatures and densities
for i in range(10):
file_out.write('-10.424 310.0\n')
# Close interface file
file_out.close()
# Archive the initial fuel interface
os.system('cp ./fuel.ifc ./fuel.ifc0')
################################
# Start the Serpent simulation #
################################
# Create a command string that will start the Serpent simulation
runcommand = sssexe+' -omp 3 ./coupledinput &'
# Execute the command string
os.system(runcommand)
#########################################
# Initialize the fuel behavior solution #
#########################################
TFU = []
BU = []
for i in range(10):
TFU.append(300.0)
BU.append(0.0)
# Reset time step
curtime = 0
curdays = 0
# Depletion step lengths (in days)
steplengths = [2, 3]
#############################
# Loop over depletion steps #
#############################
simulating = 1
while simulating == 1:
####################################################
# Picard iteration loop for current depletion step #
####################################################
iterating = 1
while iterating == 1:
###################
# Wait for signal #
###################
sleeping = 1
while sleeping == 1:
# Sleep for two seconds
time.sleep(2)
# Open file to check if we got a signal
fin = open('./com.out','r')
# Read line
line = fin.readline()
# Close file
fin.close()
# Check signal
if int(line) != -1:
if int(line) == signal.SIGUSR1:
# Got the signal to resume
sleeping = 0
elif int(line) == signal.SIGUSR2:
# Got the signal to move to next time point
iterating = 0
sleeping = 0
elif int(line) == signal.SIGTERM:
# Got the signal to end the calculation
iterating = 0
sleeping = 0
simulating = 0
else:
# Unknown signal
print "\nUnknown singal read from file, exiting\n"
# Exit
quit()
# Reset the signal in the file
file_out = open('./com.out','w')
file_out.write('-1')
file_out.close()
###########################
# Read power distribution #
###########################
# Reset power distribution
P = []
# Open output file (coolifc.out0 for first step etc.)
file_in = open('./coolifc.out{:d}'.format(curtime),'r')
# Loop over output file to read power distribution
for line in file_in:
# Split line to values
strtuple = line.split()
# Store power
P.append(float(strtuple[8]))
if iterating == 0:
# Moving to next time step
########################
# Do some archiving... #
########################
# Copy the interface and interface output to
# archive files for later examination
# Note: These are Beginning Of Step fields
os.system('cp ./fuel.ifc ./fuel.ifc{:d}'.format(curtime))
# Check if simulation has finished and break out of iterating
# loop
if (simulating == 0):
break
########################################################
# Update zone burnups (needed for material properties) #
########################################################
# Calculate fuel mass of each node (in kg)
m = (math.pi*0.4335**2*20.0)*10.424*1e-3
# Calculate initial HM mass (in kg)
# (multiply fuel mass by U wt. fraction)
mHM = m*(0.86563+0.015867)
# Get length of current time step (days)
dt = steplengths[curtime]
# Calculate burnup increment for each node
dBU = []
for power in P:
# Assume constant power throughout the BU step
dBU.append( ((power/1e6)*dt) / mHM) # in MWd/kgU
# Increment burnup of each node
for i in range(10):
BU[i] = BU[i] + dBU[i]
#######################
# Increment time step #
#######################
curdays += steplengths[curtime]
curtime += 1
#########################################
# Calculate fuel temperature solution #
#########################################
print "\nMSCS-MSCS-MSCS-MSCS-MSCS-MSCS-MSCS-MSCS-MSCS"
print "| |"
print "| Solving fuel temperature for t = {:1d} d |".format(curdays)
print "| |"
print "MSCS-MSCS-MSCS-MSCS-MSCS-MSCS-MSCS-MSCS-MSCS"
for i in range(10):
################################################################
# A polynomial expansion for fuel temperature as a function of #
# linear power and burnup #
# and burnup #
# Just a stupid power dependence so we don't need to write a #
# proper solver for fuel behavior #
################################################################
# T(bu, P) = a(bu)*LHR + b(bu)
buVec = [0.0, 10.0]
aVec = [2.0, 4.0]
bVec = [550.0, 550.0]
# Interpolate polynomial coefficients wrt. burnup
a = aVec[0] + (BU[i] - buVec[0])/(buVec[1] - buVec[0])*(aVec[1] -
aVec[0])
b = bVec[0] + (BU[i] - buVec[0])/(buVec[1] - buVec[0])*(bVec[1] -
bVec[0])
# Calculate temperature based on power
TFU[i] = a*(P[i]/20.0) + b
###########################
# Update interface #
###########################
file_out = open('./fuel.ifc','w')
# Write the header line (TYPE MAT OUT)
file_out.write('2 fuel 0\n')
# Write the mesh type
file_out.write('1\n')
# Write the mesh size (NX XMIN XMAX NY YMIN YMAX NZ ZMIN ZMAX)
file_out.write('1 -0.75 0.75 1 -0.75 0.75 10 -100 100\n')
# Write updated fuel temperatures
for i in range(10):
# Use the base density throughout the simulation
# Write density and temperature at this layer
file_out.write('-10.424 {}\n'.format(TFU[i]))
file_out.close()
############################
# Signal Serpent (SIGUSR1) #
############################
file_out = open('./com.in','w')
file_out.write(str(signal.SIGUSR1))
file_out.close()
####################################
# Check if simulation has finished #
####################################
if (simulating == 0):
break
############################
# Signal Serpent (SIGUSR1) #
############################
file_out = open('./com.in','w')
file_out.write(str(signal.SIGUSR1))
file_out.close()
input (explicit Euler)
% --- Input for MSCS testing set title "Serpent-MSCS externally coupled burnup calculation" %set acelib "<path-here>" % --- Tip: In order to quickly obtain unphysical results you can % comment out the declib and nfylib. This means that fission products % and actinides will not be produced, but the calculation sequence % proceeds otherwise normally. This can be used to check that % the calculation sequence itself runs to completion set acelib "/home/vvvillehe/XSdata/xsdir0K" %set declib "<path-here>" %set nfylib "<path-here>" % --- Fuel Pin definition: pin 1 fuel 0.4335 gas 0.442000 clad 0.502500 cool % --- Lattice (type = 1, pin pitch = 1.5): lat 10 1 0.0 0.0 1 1 1.5 1 % --- Boundary of the geometry (200 cm active length) surf 2 cuboid -0.75 0.75 -0.75 0.75 -100 100 % --- Cell definitions: cell 3 0 fill 10 -2 % Pin-cell cell 99 0 outside 2 % Outside world % --- Fuel material: mat fuel -10.424 tft 309 3000.0 burn 1 rgb 100 160 140 92235.03c -0.015867 92238.03c -0.86563 8016.03c -0.1185 % --- Axial depletion zone division for the fuel material div fuel subz 10 -200.0 200.0 % --- Cladding material: mat clad -6.55 rgb 200 200 200 40090.03c -0.98135 24052.03c -0.00100 26056.03c -0.00135 28058.03c -0.00055 50120.03c -0.01450 8016.03c -0.00125 % --- Gas gap: mat gas -1E-4 rgb 255 255 255 2004.06c 1.0 % --- Coolant (Temperature won't change, but will be given via interface): mat cool -0.90 moder lwtr 1001 rgb 150 160 240 1001.03c 0.66667 8016.03c 0.33333 5010.03c 0.0001 % --- Thermal scattering data for light water: % On-the-fly treatment for SAB-data between 474 K -- 624 K therm lwtr 520 lwj3.07t lwj3.09t % --- Axially black boundary condition set bc 3 3 1 % --- System power corresponding to a mean linear power of 200 W/cm set power 40000.0 % --- Simulation population (very small -> non-physical results) set pop 5000 50 50 % --- Maximum number of coupled calculation iterations set to 2 set ccmaxiter 2 % --- Depletion scheme constant extrapolation == explicit Euler set pcc ce % --- Depletion history (just two steps) dep daystep 2 3 % --- Geometry plot (xz) plot 2 500 1000 % --- xy-plot of fission power / thermal flux mesh 3 500 500 % --- xz-plot of fission power / thermal flux mesh 2 500 1000 % --- xy-plot of temperature distribution / thermal flux mesh 10 3 500 500 % --- xz-plot of temperature distribution / thermal flux mesh 10 2 500 1000 % --- Set material volumes for depletion zones set mvol fuel 1 11.808 fuel 2 11.808 fuel 3 11.808 fuel 4 11.808 fuel 5 11.808 fuel 6 11.808 fuel 7 11.808 fuel 8 11.808 fuel 9 11.808 fuel 10 11.808
input (Stochastic Implicit Euler)
% --- Input for MSCS testing set title "Serpent-MSCS externally coupled burnup calculation" %set acelib "<path-here>" % --- Tip: In order to quickly obtain unphysical results you can % comment out the declib and nfylib. This means that fission products % and actinides will not be produced, but the calculation sequence % proceeds otherwise normally. This can be used to check that % the calculation sequence itself runs to completion set acelib "/home/vvvillehe/XSdata/xsdir0K" %set declib "<path-here>" %set nfylib "<path-here>" % --- Fuel Pin definition: pin 1 fuel 0.4335 gas 0.442000 clad 0.502500 cool % --- Lattice (type = 1, pin pitch = 1.5): lat 10 1 0.0 0.0 1 1 1.5 1 % --- Boundary of the geometry (200 cm active length) surf 2 cuboid -0.75 0.75 -0.75 0.75 -100 100 % --- Cell definitions: cell 3 0 fill 10 -2 % Pin-cell cell 99 0 outside 2 % Outside world % --- Fuel material: mat fuel -10.424 tft 309 3000.0 burn 1 rgb 100 160 140 92235.03c -0.015867 92238.03c -0.86563 8016.03c -0.1185 % --- Axial depletion zone division for the fuel material div fuel subz 10 -200.0 200.0 % --- Cladding material: mat clad -6.55 rgb 200 200 200 40090.03c -0.98135 24052.03c -0.00100 26056.03c -0.00135 28058.03c -0.00055 50120.03c -0.01450 8016.03c -0.00125 % --- Gas gap: mat gas -1E-4 rgb 255 255 255 2004.06c 1.0 % --- Coolant (Temperature won't change, but will be given via interface): mat cool -0.90 moder lwtr 1001 rgb 150 160 240 1001.03c 0.66667 8016.03c 0.33333 5010.03c 0.0001 % --- Thermal scattering data for light water: % On-the-fly treatment for SAB-data between 474 K -- 624 K therm lwtr 520 lwj3.07t lwj3.09t % --- Axially black boundary condition set bc 3 3 1 % --- System power corresponding to a mean linear power of 200 W/cm set power 40000.0 % --- Simulation population (very small -> non-physical results) set pop 5000 50 50 % --- Depletion scheme stochastic implicit Euler with 2 iterations per step set sie 2 % --- Depletion history (just two steps) dep daystep 2 3 % --- Geometry plot (xz) plot 2 500 1000 % --- xy-plot of fission power / thermal flux mesh 3 500 500 % --- xz-plot of fission power / thermal flux mesh 2 500 1000 % --- xy-plot of temperature distribution / thermal flux mesh 10 3 500 500 % --- xz-plot of temperature distribution / thermal flux mesh 10 2 500 1000 % --- Set material volumes for depletion zones set mvol fuel 1 11.808 fuel 2 11.808 fuel 3 11.808 fuel 4 11.808 fuel 5 11.808 fuel 6 11.808 fuel 7 11.808 fuel 8 11.808 fuel 9 11.808 fuel 10 11.808
Setup
MSCS has been tested with Python 2.7.12 and Serpent 2.1.27.
- Save the contents of the MSCS.py file (above) to a file of the same name.
- Replace the absolute path to the Serpent executable on line 18 of MSCS.py.
- Save the contents of one of the input files to a file called input in the same directory where the MSCS.py file is located.
- Add the path for the cross section libraries to the input-file using the set acelib input option.
- Add the path for fission yield data to the input-file using the set nfylib input option.
- Add the path for radioactive decay data to the input-file using the set declib input option.
- The test case is now ready to run.
Note: Before running the MSCS you should familiarize yourself with finding and killing background processes in your operating system. Since MSCS runs Serpent as a background process, killing MSCS will not kill the Serpent process automatically.
Run the simulation from the folder containing both files using the command python MSCS.py
The output of the Serpent run will be printed to the terminal.- ^ J. Dufek and H. Anglart, "Derivation of a stable coupling scheme for Monte Carlo burnup calculations with the thermal-hydraulic feedback", Ann. Nucl. Energy 62, pp. 260 (2013) DOI: 10.1016/j.anucene.2013.06.025
