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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Nuclear Science and Engineering
February 2025
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Latest News
Reboot: Nuclear needs a success . . . anywhere
The media have gleefully resurrected the language of a past nuclear renaissance. Beyond the hype and PR, many people in the nuclear community are taking a more measured view of conditions that could lead to new construction: data center demand, the proliferation of new reactor designs and start-ups, and the sudden ascendance of nuclear energy as the power source everyone wants—or wants to talk about.
Once built, large nuclear reactors can provide clean power for at least 80 years—outlasting 10 to 20 presidential administrations. Smaller reactors can provide heat and power outputs tailored to an end user’s needs. With all the new attention, are we any closer to getting past persistent supply chain and workforce issues and building these new plants? And what will the election of Donald Trump to a second term as president mean for nuclear?
As usual, there are more questions than answers, and most come down to money. Several developers are engaging with the Nuclear Regulatory Commission or have already applied for a license, certification, or permit. But designs without paying customers won’t get built. So where are the customers, and what will it take for them to commit?
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.