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2025 ANS Winter Conference & Expo
November 8–12, 2025
Washington, DC|Washington Hilton
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PWR Corrosion Control in the Nuclear Industry
As many Pressurized Water Reactors (PWRs) approach or exceed 40 years of operation, maintaining asset integrity under aging infrastructure, tight outage schedules, and strict ALARA (As Low As Reasonably Achievable) mandates is a real challenge.
N. Levitz, D. E. Grosvenor, S. Vogler, F. G. Teats, N. Quattropani
Nuclear Technology | Volume 20 | Number 1 | October 1973 | Pages 60-63
Technical Note | Chemical Processing | doi.org/10.13182/NT73-A31334
Articles are hosted by Taylor and Francis Online.
A continuous fluidized-bed process for the conversion of uranium/plutonium nitrates to oxides is under development to facilitate the recycle of plutonium in the nuclear fuel cycle. The basic process consists of two steps, each performed in a separate fluid-bed reactor: (a) codenitration at 375°C of uranyl nitrate-plutonium nitrate solutions to a UO3-PuO2 powder form, and (b) reduction of the UO3-PuO2 with hydrogen at 600°C to form UO2-PuO2. Pilot-plant denitration studies with uranyl nitrate-plutonium nitrate solutions containing uranium/plutonium ratios of 50 and 4, and plutonium nitrate solution alone are described, as well as reduction of UO3-PuO2 powder. Examination of the UO3-PuO2 denitration product by autoradiographic and electron microprobe techniques showed that the PuO2 was distributed in the UO3 matrix with a high degree of homogeneity. The conversion process appears to be applicable over the entire range of uranium-plutonium concentrations and for plutonium nitrate alone. The suitability of this product for the fabrication of fuel pellets is being studied in cooperation with nuclear fuel manufacturers.