Evaluating high-alpha MOX assay improvements

Evaluating high-alpha MOX assay improvements
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Evaluating high-alpha MOX assay improvements within the multiplicity analysis framework LA-UR-24-26156 V2 24 July 2024 2024 INMM Meeting David Broughton, Daniela Henzlova, Carlos Rael, Jessica Mendez, Joe Longo, Martyn Swinhoe Los Alamos

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Evaluating high-alpha MOX assay improvements within the multiplicity analysis framework LA-UR-24-26156 V2 24 July 2024 2024 INMM Meeting David Broughton, Daniela Henzlova, Carlos Rael, Jessica Mendez, Joe Longo, Martyn Swinhoe
Los Alamos National Laboratory

Risa Suzuki, Taketeru Nagatani, Toyofumi Okada Japan Atomic Energy Agency<br>
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Context Over 35 years of bilateral Japan-U.S. collaboration on international safeguards has led to numerous advances in instrumentation and analysis

One outcome was the ENMC (Epithermal Neutron Multiplicity Counter)
JAEA uses the ENMC for NDA of large MOX items (~1-100’s g 240Pueff)
High alpha MOX items have large assay error using standard multiplicity analysis
Here we investigate this error and its mitigation 2 Samples (~0.5-700g Pu) within 1, 2, 3L canisters<br>
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Characteristics and categories of fuel materials MOX (homogenous, high α≥4)
Feed (feed material, with fluorine contamination)
Clean scrap (dry recovery process, from equipment inside gloveboxes)
Dirty scrap (wet recovery process)
Dirty scrap (no treatment)

MOX (homogeneous, low α<4)
Feed
Clean scrap (dry recovery process, from equipment inside gloveboxes)

PuO2 feed (feed material, with fluorine contamination)


Items are either full (~50-700 g Pu) or samples (~1 g Pu) taken from full items 3<br>