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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Hash Hashemian: Visionary leadership
As Dr. Hashem M. “Hash” Hashemian prepares to step into his term as President of the American Nuclear Society, he is clear that he wants to make the most of this unique moment.
A groundswell in public approval of nuclear is finding a home in growing governmental support that is backed by a tailwind of technological innovation. “Now is a good time to be in nuclear,” Hashemian said, as he explained the criticality of this moment and what he hoped to accomplish as president.
C. L. Brown, L. C. Davenport, D. R Oden
Nuclear Technology | Volume 18 | Number 2 | May 1973 | Pages 109-114
Technical Paper | A Review of Plutonium Utilization in Thermal Reactors / Reactor | doi.org/10.13182/NT73-A31282
Articles are hosted by Taylor and Francis Online.
The nuclear criticality safety aspects of light water reactor (Pu,U)O2 fuel fabrication have been reviewed. Conclusions are as follows: 1. Criticality safety limitations will present a major design challenge in those parts of the plant where plutonium and plutonium-uranium solutions are processed. In particular, the requirement of large vessel volume to achieve homogeneous plutonium-uranium blending will be complicated by the restrictive criticality safety limits necessary on vessel dimensions. Special vessel design, such as annular geometry, and fixed nuclear poisons are possible innovations to overcome this problem. 2. Once the PuO2 and UO2 are mixed and in dry powder form, plant throughput should proceed at a reasonable rate and criticality safety will not necessarily limit operations. 3. In dry operations, radiation protection limitations are likely to be more restrictive than criticality safety limitations. In other words, criticality safety limits will not be determining factors for process control, since the fuel will be well confined in glove boxes and handled in relatively small batches for radiation protection considerations. 4. The fact that plutonium recycle fuel will be fabricated in sealed glove boxes will make it more feasible to base criticality safety on limits for unmoderated fuel, in certain parts of the plant, than is now possible in UO2 fuel fabrication plants. 5. The basic critical masses and dimensions applicable to the fabrication of plutonium recycle fuel are expected to be only slightly more restrictive than those for light water reactor UO2 fuel.