Next-generation online MC and A technologies for reprocessing plants
- Pacific Northwest National Laboratory, PO Box 999, Richland, WA, 99352 (United States)
- Nuclear Engineering Program, Mechanical Engineering Department, Ohio State University, Columbus, OH, 43210 (United States)
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 gamma ray 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 next generation online materials control and accountability measures. (authors)
- Research Organization:
- American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 20979750
- Resource Relation:
- Conference: Advanced nuclear fuel cycles and systems (GLOBAL 2007), Boise - Idaho (United States), 9-13 Sep 2007; Other Information: Country of input: France; 16 refs; Related Information: In: Proceedings of GLOBAL 2007 conference on advanced nuclear fuel cycles and systems, 1873 pages.
- Country of Publication:
- United States
- Language:
- English
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