کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
1739852 1017311 2016 11 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Development of Industrial-Scale Fission 99Mo Production Process Using Low Enriched Uranium Target
ترجمه فارسی عنوان
توسعه فرآیند تولید 99 میلی مولار صنعتی با استفاده از هدف اورانیوم غنی شده کم
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی انرژی هسته ای و مهندسی
چکیده انگلیسی

Molybdenum-99 (99Mo) is the most important isotope because its daughter isotope, technetium-99m (99mTc), has been the most widely used medical radioisotope for more than 50 years, accounting for > 80% of total nuclear diagnostics worldwide. In this review, radiochemical routes for the production of 99Mo, and the aspects for selecting a suitable process strategy are discussed from the historical viewpoint of 99Mo technology developments. Most of the industrial-scale 99Mo processes have been based on the fission of 235U. Recently, important issues have been raised for the conversion of fission 99Mo targets from highly enriched uranium to low enriched uranium (LEU). The development of new LEU targets with higher density was requested to compensate for the loss of 99Mo yield, caused by a significant reduction of 235U enrichment, from the conversion. As the dramatic increment of intermediate level liquid waste is also expected from the conversion, an effective strategy to reduce the waste generation from the fission 99Mo production is required. The mitigation of radioxenon emission from medical radioisotope production facilities is discussed in relation with the monitoring of nuclear explosions and comprehensive nuclear test ban. Lastly, the 99Mo production process paired with the Korea Atomic Energy Research Institute's own LEU target is proposed as one of the most suitable processes for the LEU target.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Nuclear Engineering and Technology - Volume 48, Issue 3, June 2016, Pages 613–623
نویسندگان
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