Neutron flux
Three levels of calculation, each building on the previous:
| Function | What it computes | Considers geometry? |
|---|---|---|
calculate_transmission |
Material attenuation only (exp(-Sigma*t)) | No |
calculate_flux |
S / (4piR^2) * exp(-Sigma*t) * B | Yes (inverse square law) |
calculate_dose |
Flux * ICRP-116 dose coefficient | Yes (inverse square law) |
The same calculate_flux interface applies to neutrons; just create a neutron Source.
Example
import rad_point_kernel as rpk
iron = rpk.Material(composition={"Fe": 1.0}, density=7.874)
layers = [
rpk.Layer(thickness=1000), # 10 m void
rpk.Layer(thickness=10, material=iron), # 10 cm iron
]
source = rpk.Source(particle="neutron", energy=14.1e6)
result = rpk.calculate_flux(source_strength=1e12, layers=layers, source=source)
print(f"Flux: {result.uncollided_flux} neutrons/cm2/s")
print(f"Transmission: {result.transmission_fraction}")
print(f"Optical thickness: {result.optical_thickness}")
print(f"Distance: {result.total_distance_cm} cm")
The returned CalcResult has the same properties as in the photon case; see Flux (photon).
With a manual build-up factor
import rad_point_kernel as rpk
iron = rpk.Material(composition={"Fe": 1.0}, density=7.874)
layers = [
rpk.Layer(thickness=1000),
rpk.Layer(thickness=10, material=iron),
]
source = rpk.Source(particle="neutron", energy=14.1e6)
B_flux = 3.0
result = rpk.calculate_flux(
source_strength=1e12,
layers=layers,
source=source,
buildup=rpk.BuildupModel.constant(B_flux),
)
print(f"Flux (B={B_flux}): {result.uncollided_flux} neutrons/cm2/s")
print(f"Applied build-up: {result.buildup_factor}")
See Calculate build-up with MC for how to compute B from first principles.