Year
2014
Abstract
The spent fuel characterization needs of the International Atomic Energy Agency (IAEA) and the National Nuclear Security Administration (NNSA) Next Generation Safeguards Initiative (NGSI) are important factor s in determining the R& D that is sponsored by the NNSA Defense Nuclear Nonproliferation Research and Development (DNN R&D) Office. Several technologies are being developed to directly and quantitatively measure Pu in spent fuel: gamma - ray mirrors, delayed gamma, differential di e away, microcalorimetry and the ultra - high rate germanium detector. Additional work is being done in partial defect detection and neutron detector development to replace 3 He detectors. Brief descriptions of each technology are presented.