TY - GEN
T1 - Radioisotope power source dose estimation tool (RPS-DET)
AU - Smith, Michael B.R.
N1 - Publisher Copyright:
© 2018 IEEE.
PY - 2018/6/25
Y1 - 2018/6/25
N2 - The purpose of this work is to develop a radioisotope power source dose estimation tool (RPS-DET) capable of rapidly predicting accurate neutron and gamma-ray flux/dose implications from various radioisotope power sources (RPSs). RPS-DET can use this information to calculate the flux/dose incident on or absorbed by nearby humans, materials, and electronics over a complex mission lifetime. This simulation tool uses a Matlab user interface to combine common geometry scenarios for traditional and new RPS design configurations to write a particle-transport simulation using Monte Carlo N-Particle (MCNP) 6, which provides results that are automatically post-processed for interactive analysis. The user defines the average age of the PuO2 fuel, which determines the appropriate time-dependent gamma-ray and neutron spectra, along with the desired RPS and local environment for the simulation. Results for a given simulation are gamma-ray, neutron, and combined flux spectra, whole-body effective dose for humans, and absorbed dose in silicon for electronics. This work has been benchmarked against measurements of existing RPS units and has been determined to predict neutron and gamma flux, absorbed dose, and dose equivalent within 50% of simulation uncertainties.
AB - The purpose of this work is to develop a radioisotope power source dose estimation tool (RPS-DET) capable of rapidly predicting accurate neutron and gamma-ray flux/dose implications from various radioisotope power sources (RPSs). RPS-DET can use this information to calculate the flux/dose incident on or absorbed by nearby humans, materials, and electronics over a complex mission lifetime. This simulation tool uses a Matlab user interface to combine common geometry scenarios for traditional and new RPS design configurations to write a particle-transport simulation using Monte Carlo N-Particle (MCNP) 6, which provides results that are automatically post-processed for interactive analysis. The user defines the average age of the PuO2 fuel, which determines the appropriate time-dependent gamma-ray and neutron spectra, along with the desired RPS and local environment for the simulation. Results for a given simulation are gamma-ray, neutron, and combined flux spectra, whole-body effective dose for humans, and absorbed dose in silicon for electronics. This work has been benchmarked against measurements of existing RPS units and has been determined to predict neutron and gamma flux, absorbed dose, and dose equivalent within 50% of simulation uncertainties.
UR - http://www.scopus.com/inward/record.url?scp=85049866414&partnerID=8YFLogxK
U2 - 10.1109/AERO.2018.8396766
DO - 10.1109/AERO.2018.8396766
M3 - Conference contribution
AN - SCOPUS:85049866414
T3 - IEEE Aerospace Conference Proceedings
SP - 1
EP - 19
BT - 2018 IEEE Aerospace Conference, AERO 2018
PB - IEEE Computer Society
T2 - 2018 IEEE Aerospace Conference, AERO 2018
Y2 - 3 March 2018 through 10 March 2018
ER -