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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
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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 Technology
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Latest News
Bipartisan nuclear waste bill introduced in U.S. House
U.S. representatives Mike Levin (D., Calif.) and August Pfluger (R., Texas) have introduced the bipartisan Nuclear Waste Administration Act of 2024, which would establish an independent agency to manage the country’s nuclear waste.
In addition to establishing a new, single-purpose administration to manage the back end of the nuclear fuel cycle, the bill would direct a consent-based siting process for nuclear waste facilities and ensure reliable funding for managing nuclear waste by providing access to the Nuclear Waste Fund. According to Pfluger and Levin, the bill’s provisions are in line with recommendations from the Blue Ribbon Commission on America’s Nuclear Future.
Paul David Bottomley, Michel Coquerelle
Nuclear Technology | Volume 87 | Number 1 | August 1989 | Pages 120-136
Technical Paper | TMI-2: Materials Behavior / Nuclear Safety | doi.org/10.13182/NT89-A27642
Articles are hosted by Taylor and Francis Online.
Samples of the bores obtained from the melted core of the Three Mile Island Unit 2 (TMI-2) reactor were investigated as part of the TMI-2 accident evaluation program. The samples included fuel rod segments, control rod cladding, melted core rocks, and powder debris from various bores into the reactor core. The microstructure of the specimens was determined by examination and analysis of surface and cross section by means of electro-optical techniques (including energy-dispersive X-ray scanning electron microscopy and microprobe analysis). Gamma spectroscopy and a fission product release study were also performed on the specimens. The melted core rock specimens obtained from the G12 bores were mostly porous ceramic mixtures of uranium and zirconium oxides in the form of a fine eutectic of UO2- and ZrO2-rich phases and oxidized ferrous material derived from the stainless steel components. The rock specimens showed variations in porosity and ferrous content but a similar UO2-ZrO2 eutectic structure. Fission product analysis of the fuel segments and rocks indicated relatively low levels of activity due to fission products such as I37Cs, 106Ru, I54Eu, and fuel irradiation products. No volatile 129I was detected, but most other products displayed some retention in the melted core samples. According to whether eutectics were formed between Zr(O) and UO2 or ZrO2 and UO2 (i.e., the oxygen potential in the core), reference to the phase diagrams suggests temperatures of 2173 to 2873 K (1900 to 2600°C) for substantial periods and even up to 3073 K (2800°C) (U02 melting point) for the completely melted core specimens. Agglomerate specimens indicate lower temperatures [∼1673 K (1400°C), the melting point of stainless steel] and shorter excursion times at the edge of the melt zone. The remaining fuel rod segments showed very little change, indicating that the severe overheating is localized to the central part of the reactor pile.