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Fuel Cycle & Waste Management
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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
Smitha Manohar, J. N. Sharma, B. V. Shah, P. K. Wattal
Nuclear Science and Engineering | Volume 156 | Number 1 | May 2007 | Pages 96-102
Technical Paper | doi.org/10.13182/NSE07-A2688
Articles are hosted by Taylor and Francis Online.
In-house R&D studies have resulted in the development of processes for the bulk separation of trivalent actinides and lanthanides from radioactive high-level liquid waste. Synthesis of solvents, namely, n-octyl (phenyl)-N,N-di-isobutyl carbamoyl methyl phosphine oxide and diglycolamide-based tetra (2-ethylhexyl) diglycolamide (TEHDGA), at the required purity has been carried out, and a suitable process for their respective use in actual application has been developed. Inactive scale engineering runs comprised of simultaneous extraction and stripping operations were carried out to establish the process on an engineering scale, including reuse of the solvent system. The composition of surrogate high-level waste (HLW) used at engineering-scale studies corresponds to first-cycle raffinate from reprocessing of long-cooled pressurized heavy water reactor fuel with a burnup of 6500 MWd/tonne. Since trivalent lanthanides and actinides exhibits similar extraction behavior at higher acidity, cerium and lanthanum were only used in making surrogate HLW to represent all the trivalent lanthanides and actinides. Indigenously developed mixer-settlers using a passive system of mixing were used for these runs. Over a period of ~10 h, ~300 l of surrogate HLW solutions were contacted with solvent. The results of such repeated trials have shown near-total removal of cerium and lanthanum (>99.8% and 97%, respectively) at aqueous-to-organic ratio of 2.5:1 for a TEHDGA system. As the distribution coefficient values for trivalent actinide (241Am) are found to be significantly higher than those for trivalent lanthanides for both of the solvent systems under consideration, it can be inferred that separation of trivalent actinides along with lanthanides could be feasible using these solvent systems.