²⁴¹Am Ingrowth and Its Effect on Internal Dose

Journal Article · Fri Jul 01 00:00:00 EDT 2016 · Health Physics

DOI:https://doi.org/10.1097/HP.0000000000000511· OSTI ID:1368540

Konzen, Kevin ^[1]

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1. CH2M-WG Idaho, LLC, Idaho Falls, ID (United States)

Generally, plutonium has been manufactured to support commercial and military applications involving heat sources, weapons and reactor fuel. This work focuses on three typical plutonium mixtures, while observing the potential of ²⁴¹Am ingrowth and its effect on internal dose. The term “ingrowth” is used to describe ²⁴¹Am production due solely from the decay of ²⁴¹Pu as part of a plutonium mixture, where it is initially absent or present in a smaller quantity. Dose calculation models do not account for ²⁴¹Am ingrowth unless the ²⁴¹Pu quantity is specified. This work suggested that ²⁴¹Am ingrowth be considered in bioassay analysis when there is a potential of a 10% increase to the individual’s committed effective dose. It was determined that plutonium fuel mixtures, initially absent of ²⁴¹Am, would likely exceed 10% for typical reactor grade fuel aged less than 30 years; however, heat source grade and aged weapons grade fuel would normally fall below this threshold. In conclusion, although this work addresses typical plutonium mixtures following separation, it may be extended to irradiated commercial uranium fuel and is expected to be a concern in the recycling of spent fuel.

• Research Organization: Idaho National Lab. (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE Idaho Operations Office (IO)
• Grant/Contract Number: AC07-051D14516
• OSTI ID: 1368540
• Journal Information: Health Physics, Vol. 111, Issue 1; ISSN 0017-9078
• Publisher: Health Physics Society
• Country of Publication: United States
• Language: English

Related Subjects

61 RADIATION PROTECTION AND DOSIMETRY
241Am
biokinetics
dosimetry
internal
plutonium