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- Maritime reactor waste disposal studies :solidification of ion-exchange resin with Portland cement for radioactive waste disposal
- Purification of kilocurie quantities of promethium-147 by ion exchange
- Ion exchange purification of promethium-147 and its separation from americium-241, with diethylenetriaminepentaacetic acid as the eluant
- Proposed head-end treatments of PUREX-1WW waste for fission product recovery by ion exchange
- Recovery of plutonium and other transuranium elements from irradiated plutonium-aluminum alloy by ion exchange methods
- Recovery of ¹³⁷Cs from fission-prodcut wastes and transport by an aluminosillicate ion exchanger