Use of Self-Interrogation Neutron Resonance Densitometry to Measure the Fissile Content in a BWR 9×9 Spent Fuel Assembly

Center for Nuclear Security Science and Policy Initiatives

Texas A&M Engineering Experiment Station

Use of Self-Interrogation Neutron Resonance Densitometry to Measure the Fissile Content in a BWR 9×9 Spent Fuel Assembly

Citation:

A. M. LaFleur, H. O. Menlove, W. S. Charlton, M. T. Swinhoe, “Use of Self-Interrogation Neutron Resonance Densitometry to Measure the Fissile Content in a BWR 9×9 Spent Fuel Assembly”, 33rd ESARDA Annual Meeting: Symposium on Safeguards and Nuclear Material Management, May 16–20, 2011, Budapest, Hungary.

Associated Project:

1. Development of Self-Interrogation Neutron Resonance Densitometry (SINRD) to Measure the Fissile Content in Nuclear Fuel