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Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
Wallace W. Schulz
Nuclear Technology | Volume 13 | Number 2 | February 1972 | Pages 159-167
Technical Paper | Chemical Processing | doi.org/10.13182/NT72-A31050
Articles are hosted by Taylor and Francis Online.
Irradiation (60Co source) tests were performed to determine effects of radiolysis of HDEHP [bis(2-ethylhexyl)phosphoric acid] solvents. (An HDEHP-TBP -kerosene extractant is used in the Hanford B Plant to extract 90Sr from Purex process high-level waste). Irradiation to 230 to 350 Wh/liter destroys only small (∼6%) amounts of HDEHP; the principal radiolytic effect is a two- to threefold decrease in strontium extraction capacity. This effect is ascribed to polymerization of HDEHP with itself and/or with H2MEHP [mono (2-ethyIhexyl)phosphoric acid], a primary radiolysis product. Dilute NaOH and Na2CO3 solutions wash H2MEHP from irradiated HDEHP extractants; however, only with solvents irradiated in the absence of any aqueous phase do such washes improve strontium extraction properties. Addition of unirradiated HDEHP to irradiated HDEHP solvents increases their ability to extract strontium; this simple procedure is used to maintain the strontium extraction capacity of the B Plant solvent at a suitable level. Performance and properties of plant solvent are in general agreement with those anticipated from 60Co irradiation tests.