TY - GEN
T1 - MCNP simulation of discrete gamma-ray spectra for PGNAA applications
AU - Seabury, E. H.
AU - Wharton, C. J.
AU - Caffrey, A. J.
N1 - Publisher Copyright:
© 2015 IEEE.
PY - 2016/10/3
Y1 - 2016/10/3
N2 - Prompt Gamma Neutron Activation Analysis (PGNAA) systems, such as Idaho National Laboratory's PINS system [1], are used by the U.S. Army to identify chemical warfare materiel (CWM) and explosives in recovered munitions. The wide variety of fill chemicals and assessment conditions for these munitions makes Monte Carlo modeling of the gamma spectra attractive in order to assess the impact of these variations on identification algorithms as have recent improvements to the prompt gamma production in the nuclear data libraries for low-Z chemical elements. The availability of High Performance Computing (HPC) systems makes these simulations more rapid than laboratory measurements, and can be very useful provided the codes and associated data libraries accurately reproduce the laboratory measurements. We present here a comparison of simulation results using the MCNP6 code [2] and the ENDF/B-VII libraries with laboratory measurements using two different neutron sources, a californium-252 source and a deuterium-deuterium (DD) neutron generator.
AB - Prompt Gamma Neutron Activation Analysis (PGNAA) systems, such as Idaho National Laboratory's PINS system [1], are used by the U.S. Army to identify chemical warfare materiel (CWM) and explosives in recovered munitions. The wide variety of fill chemicals and assessment conditions for these munitions makes Monte Carlo modeling of the gamma spectra attractive in order to assess the impact of these variations on identification algorithms as have recent improvements to the prompt gamma production in the nuclear data libraries for low-Z chemical elements. The availability of High Performance Computing (HPC) systems makes these simulations more rapid than laboratory measurements, and can be very useful provided the codes and associated data libraries accurately reproduce the laboratory measurements. We present here a comparison of simulation results using the MCNP6 code [2] and the ENDF/B-VII libraries with laboratory measurements using two different neutron sources, a californium-252 source and a deuterium-deuterium (DD) neutron generator.
UR - https://www.scopus.com/pages/publications/84994111821
U2 - 10.1109/NSSMIC.2015.7581848
DO - 10.1109/NSSMIC.2015.7581848
M3 - Conference contribution
AN - SCOPUS:84994111821
T3 - 2015 IEEE Nuclear Science Symposium and Medical Imaging Conference, NSS/MIC 2015
BT - 2015 IEEE Nuclear Science Symposium and Medical Imaging Conference, NSS/MIC 2015
PB - Institute of Electrical and Electronics Engineers Inc.
T2 - 2015 IEEE Nuclear Science Symposium and Medical Imaging Conference, NSS/MIC 2015
Y2 - 31 October 2015 through 7 November 2015
ER -