Next-generation online MC&A technologies for reprocessing plants

L. E. Smith, J. M. Schwantes, J. J. Ressler, M. Douglas, K. A. Anderson, C. G. Fraga, C. Durst, C. Orton, R. Christensen

Research output: Chapter in Book/Report/Conference proceedingConference contribution

3 Scopus citations


As power-production nuclear fuel cycles propagate across the globe, a new generation of measurement technologies is needed to support safeguards monitoring of fuel reprocessing facilities. This paper describes the simulation and analysis of two potential technologies for meeting the challenges of 1) direct measurement of fissile isotopic content in irradiated fuel to detect partial defects, and 2) near-real-time monitoring of process chemistry to detect protracted diversion scenarios. Lead slowing-down spectroscopy is the core of the spent fuel assay technology and multi-isotope indicators via high-resolution gammaray spectroscopy are the foundation of the process chemistry verification approach. The safeguards context and methods for each technology are described and the results of preliminary performance studies are presented. The quantitative results for both studies are promising but more comprehensive analysis and empirical validation is needed to adequately assess their potential value as nextgeneration online materials control and accountability measures.

Original languageEnglish (US)
Title of host publicationGLOBAL 2007
Subtitle of host publicationAdvanced Nuclear Fuel Cycles and Systems
Number of pages10
StatePublished - 2007
EventGLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems - Boise, ID, United States
Duration: Sep 9 2007Sep 13 2007

Publication series

NameGLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems


ConferenceGLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems
Country/TerritoryUnited States
CityBoise, ID

All Science Journal Classification (ASJC) codes

  • Energy Engineering and Power Technology
  • Fuel Technology
  • Nuclear Energy and Engineering


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