A.M. LaFleur, W.S. Charlton, H.O. Menlove, and M. Swinhoe,
"Development of Self-Interrogation Neutron Resonance Densitometry (SINRD) to Measure the 235U and 239Pu Content in a PWR 17x17 Spent Fuel Assembly,"
Proceedings of 31st Annual Meeting of ESARDA
, May 26-28, 2009, Vilnius, Lithuania.
The use of Self-Interrogation Neutron Resonance Densitometry
(SINRD) to measure the 235U and 239Pu content in a PWR spent fuel
assembly was investigated via Monte Carlo N-Particle eXtended
transport code (MCNPX) simulations. The sensitivity of SINRD is
based on using the same fissile materials in the fission chambers
as are present in the fuel because the effect of resonance
absorption lines in the transmitted flux is amplified by the
corresponding (n,f) reaction peaks in fission chamber. These
simulations utilize the 244Cm spontaneous fission neutrons to
self-interrogate the fuel pins. The amount of resonance absorption
of these neutrons in the fuel can be measured using 235U and 239Pu
fission chambers placed adjacent to the assembly. We used ratios of
different fission chambers to reduce the sensitivity of the
measurements to extraneous material present in fuel. The
development of SINRD to measure the fissile content in spent fuel
is of great importance to the improvement of nuclear safeguards and
material accountability. Future work includes the use of this
technique to measure the fissile content in FBR spent fuel and
heavy metal product from reprocessing methods.
Associated Project(s):Development of Self-Interrogation Neutron Resonance Densitometry (SINRD) to Measure the Fissile Content in Nuclear Fuel