ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
Standards Program
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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August 2024
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Latest News
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.
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.