Gas-phase molybdenum-99 separation from uranium dioxide by fluoride volatility using nitrogen trifluoride

Author:

McNamara Bruce K.123ORCID,O'Hara Matthew J.123ORCID,Clark Richard A.123ORCID,Morrison Samuel S.123ORCID,Soderquist Chuck Z.123ORCID,Scheele Randall D.423ORCID

Affiliation:

1. Pacific Northwest National Laboratory

2. Richland

3. USA

4. Flibe Energy

Abstract

Data demonstrates large variance in the volatilization temperatures of MoO2 (likely as MoF6) vs. UO2 (as UF6). This forms the basis of a gas-phase separation of 99Mo from U.

Publisher

Royal Society of Chemistry (RSC)

Subject

General Chemical Engineering,General Chemistry

Reference22 articles.

1. R. M.Ball , Characteristics of nuclear reactors used for the production of molybdenum-99 , Production Technologies for Molybdenum-99 and Technetium-99m, IAEA-TECDOC-1065 , International Atomic Energy Agency , Vienna , 1999 , pp. 5–17

2. G. F.Vandegrift and J. L.Snelgrove , et al., Converting targets and processes for fission-product molybdenum-99 from high- to low-enriched uranium , Production Technologies for Molybdenum-99 and Technetium-99m, IAEA-TECDOC-1065 , International Atomic Energy Agency , Vienna , 1999 , pp. 25–74

3. Modification of Targets and Processes for Conversion of 99Mo Production from High- to Low-Enriched Uranium

4. Fluorex reprocessing system for the thermal reactors cycle and future thermal/fast reactors (coexistence) cycle

5. J.Uhlir , An experience on dry nuclear fuel reprocessing in the Czech Republic , in 5th International Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation , Czech Republic , 1999

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