Radiation Safety
Correct for air density - useful for vented ion chambers
Calculate fractional solid angle for disk to disk
Correct activity-dependent value based on radioactive decay.
Number of half-lives past
Time to decay to target radioactivity.
Calculate half-life based on two data points
half-value layer and tenth-value layer computations
MCNP Cone Opening Parameter
Copy and paste MCNP tally fluctuation charts
Rotation matrices for transformations in MCNP
Make mesh tally size settings for MCNP
Convert histogram data to average points and plot as spectrum.
Copy and paste MCNP output spectral data for use with `mcnp_plot_out_s...
Copy and paste MCNP output spectral data to directly plot
energy distribution histogram from pasted data
Produce MCNP source terms from ICRP 107 data
energy distribution histogram entries
energy distribution histogram from pasted data
Produce MCNP source terms from ICRP 107 data except beta
Solid Angle Correction for Neutron Detectors with Point Source
Pipe operator
radsafer: Radiation Safety
Ratemeter Simulation
Search for radioisotopes that dominate a specified energy bin
Find a potential precursor of a radionuclide @description Find a poten...
Screen radionuclide data to find matches to decay mode, half-life, and...
Quick table of Radionuclide Data from the RadData package
Plot results of RN_search functions
Plot radionuclide emission spectra.
Save radionuclide emission spectra.
Search for alpha
Search for beta
Search for photon
Specific Activity
Count Room Scaler Simulation
Stay time for radiation work.
Estimate tau parameter for ratemeter_sim
Provides functions for radiation safety, also known as "radiation protection" and "radiological control". The science of radiation protection is called "health physics" and its engineering functions are called "radiological engineering". Functions in this package cover many of the computations needed by radiation safety professionals. Examples include: obtaining updated calibration and source check values for radiation monitors to account for radioactive decay in a reference source, simulating instrument readings to better understand measurement uncertainty, correcting instrument readings for geometry and ambient atmospheric conditions. Many of these functions are described in Johnson and Kirby (2011, ISBN-13: 978-1609134198). Utilities are also included for developing inputs and processing outputs with radiation transport codes, such as MCNP, a general-purpose Monte Carlo N-Particle code that can be used for neutron, photon, electron, or coupled neutron/photon/electron transport (Werner et. al. (2018) <doi:10.2172/1419730>).