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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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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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?
August W. Cronenberg, Michael A. Grolmes
Nuclear Technology | Volume 27 | Number 3 | November 1975 | Pages 394-410
Technical Paper | Fuel | doi.org/10.13182/NT75-A24313
Articles are hosted by Taylor and Francis Online.
To understand the phenomenology and consequences of a hypothetical mild (∼50¢ to $5/sec) overpower transient for a liquid-metal fast breeder reactor (LMFBR), a continuing series of in-pile fuel-failure experiments has been performed in the TREA T reactor for both fresh and preirradiated pins. The voiding history obtained from the failure of a fresh fuel element has been shown to result from a mild fuel-coolant-interaction process. However, preirradiated pins are accompanied by significant fission gas retention, which leads to a difference in failure criterion and voiding mechanism. Thus, the dynamics of coolant expulsion, following the failure of preirradiated pins under overpower transient conditions, must include the effects of gas discharge to the coolant channel. The flow transient for preirradiated fuel elements, brought to failure in a flowing sodium environment, was analyzed in terms of fission-gas-induced voiding. The analytic approach was based on single-phase isothermal expansion of the fis-sion-gas bubble, which was assumed to be ideal and to fill the coolant-channel cross section uniformly. Gas discharge through the cladding breach was calculated using either the equation for critical or for subcritical flow, depending on the pin-to-bubble pressure ratio. The coolant was considered incompressible. A parametric study indicates that the initial breach size is quite small, initiating a relatively slow rate of voiding without initial inlet-flow reversal. However, ∼100 msec after failure, rapid coolant expulsion and inlet-flow reversal occurs. To account for this condition, fission-gas communication between the storage plenum and core regions of the pin must be assumed, since the free gas inventory within the fueled section alone is quite small. At the time of flow reversal, however, significant melting and some vaporization of the fuel has occurred; thus, coolant expulsion by fuel-coolant interaction and/or fuel vapor pressure cannot be discounted. The release of such fission gas, however, will affect the energetics of fuel-coolant interaction and fuel sweepout; thus, gas effects must be taken into account in the analysis of LMFBR overpower transients.