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The Use of Self-induced XRF to Quantify the Pu Content in MOX Spent Nuclear Fuel

The Use of Self-induced XRF to Quantify the Pu Content in MOX Spent Nuclear Fuel

Citation:

A.A. Solodov, W.S. Charlton, S. Saavedra, L. Khodalev, “The Use of Self-induced XRF to Quantify the Pu Content in MOX Spent Nuclear Fuel”, 51st Annual Meeting for the Institute of Nuclear Materials Management, Baltimore, Maryland, July 11-15, 2010.

Associated Projects:

1. Development of Advanced Safeguards Measurement Techniques Using the Coupled End-to-End (CETE) Demonstration at ORNL,