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Computing Reaction Rates on a Block.
In this example, a set of 1-group reaction rates (in #/s) are evaluated for a dummy fuel block containing UZr fuel, HT9 structure, and sodium coolant. A dummy multigroup flux is applied.
This example also demonstrates how to build a reactor model from code alone rather than relying upon input files.
import matplotlib.pyplot as plt
import numpy as np
from armi import configure, nuclideBases, settings
from armi.materials import ht9
from armi.materials import sodium
from armi.materials import uZr
from armi.nuclearDataIO.cccc import isotxs
from armi.reactor import assemblies
from armi.reactor import blocks
from armi.reactor import blueprints
from armi.reactor import geometry
from armi.reactor import grids
from armi.reactor import reactors
from armi.reactor.components import Circle
from armi.reactor.components import DerivedShape
from armi.reactor.components import Hexagon
from armi.reactor.flags import Flags
from armi.tests import ISOAA_PATH
configure(permissive=True)
def _addFlux(b):
"""Add dummy 33-group flux to the block."""
# fmt: off
b.p.mgFlux = [
1.6e+11, 2.3e+12, 1.1e+13, 2.6e+13, 4.6e+13, 7.9e+13, 1.4e+14, 2.2e+14,
2.3e+14, 2.7e+14, 2.2e+14, 1.7e+14, 1.3e+14, 1.4e+14, 7.5e+13, 3.2e+13,
2.2e+13, 6.3e+12, 2.2e+13, 1.2e+13, 5.2e+12, 1.5e+12, 1.4e+12, 2.9e+11,
7.4e+10, 5.5e+10, 1.9e+10, 5.0e+09, 3.6e+09, 8.8e+08, 4.3e+09, 1.3e+09,
6.0e+08
]
# fmt: on
def createDummyReactor():
"""
Create a dummy reactor with a single fuel assembly and a single fuel block.
Often, a reactor model like this is built directly from input files rather
than from code as done here.
"""
bp = blueprints.Blueprints()
cs = settings.Settings()
r = reactors.Reactor("Reactor", bp)
r.add(reactors.Core("Core"))
r.core.spatialGrid = grids.HexGrid.fromPitch(1.0)
r.core.spatialGrid.symmetry = geometry.SymmetryType(
geometry.DomainType.THIRD_CORE, geometry.BoundaryType.PERIODIC
)
r.core.spatialGrid.geomType = geometry.GeomType.HEX
r.core.spatialGrid.armiObject = r.core
r.core.setOptionsFromCs(cs)
# Create a single fuel assembly
a = assemblies.HexAssembly("fuel assembly")
a.spatialGrid = grids.AxialGrid.fromNCells(1)
a.spatialLocator = r.core.spatialGrid[1, 0, 0]
# Create a single fuel block
b = blocks.HexBlock("fuel block")
b.setType("fuel")
# Create a single fuel component with UZr fuel.
dims = {"Tinput": 20, "Thot": 900, "id": 0.0, "od": 2.9, "mult": 7}
c = Circle("fuel", uZr.UZr(), **dims)
b.add(c)
# Create a single structure component with HT9.
dims = {"Tinput": 20, "Thot": 600, "op": 16.0, "ip": 15.0, "mult": 1}
c = Hexagon("structure", ht9.HT9(), **dims)
b.add(c)
# Fill in the rest of the block with sodium coolant.
dims = {"Tinput": 600, "Thot": 600}
c = DerivedShape("coolant", sodium.Sodium(), **dims)
b.add(c)
a.add(b)
r.core.add(a)
_addFlux(b)
return r
# Create a dummy reactor with the function defined above.
r = createDummyReactor()
# Add an example cross section library to the reactor core
r.core.lib = isotxs.readBinary(ISOAA_PATH)
b = r.core.getFirstBlock(Flags.FUEL)
b.expandElementalToIsotopics(nuclideBases.byName["NA"])
# Iterate over a few nuclides/elements in the XS library
# and collect the total reaction rates in #/s.
allRates = []
nucNames = ["U235", "U238", "FE", "NA23"]
for nucName in nucNames:
rateData = b.getReactionRates(nucName)
rateLabels = sorted(rateData.keys()) # will be constant
allRates.append([rateData[k] for k in rateLabels])
# plot the reaction rates as a bar graph
fig, ax = plt.subplots()
width = 1.0 / len(rateLabels)
offset = 0.0
for nucName, nucRates in zip(nucNames, allRates):
ax.bar(
np.arange(len(rateLabels)) + width + offset,
nucRates,
width=width,
label=nucName,
)
offset += width
ax.set_xticks(np.arange(len(rateLabels)) + 0.5)
ax.set_xticklabels(rateLabels)
# Add little divider lines between reactions for clarity
for border in np.arange(len(rateLabels) - 1):
ax.axvline(border + 1, ls="--", alpha=0.4, color="k")
ax.set_xlim([0, len(rateLabels)])
plt.yscale("log")
plt.legend()
plt.title("Reaction rates")
plt.xlabel("Reaction type")
plt.ylabel("Reaction rate (1/s)")
plt.show()
Total running time of the script: ( 0 minutes 0.405 seconds)