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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Fusion Science and Technology
Latest News
Retrieval of nuclear waste canisters from a borehole
Borehole disposal of spent nuclear fuel (SNF) and high-level waste (HLW) uses off-the-shelf directional drilling technology developed and commercialized by the oil and gas sectors. It is a technology that has been gaining traction in recent years in the nuclear industry. Disposal can be done in one or more boreholes (including an array) drilled into suitable sedimentary, igneous, or metamorphic host rocks. Waste is encapsulated in specialized corrosion-resistant canisters, which are placed end to end in disposal sections of relatively small-diameter boreholes that have been cased and fluid-filled. After emplacement, the vertical access hole is plugged and backfilled as an engineered barrier.
Kei-Ichiro Shibata, Koichi Maki, Michio Otsuka, Takashi Inoue
Fusion Science and Technology | Volume 30 | Number 1 | September 1996 | Pages 50-62
Technical Paper | Shielding | doi.org/10.13182/FST96-A30762
Articles are hosted by Taylor and Francis Online.
As applied to the common design of the neutral beam injection (NBI) system in the International Thermonuclear Experimental Reactor (ITER) Conceptual Design Activity, a design is proposed and examined that reduces the equivalent dose rate of the NBI system in order to enable access to the outside of the injector. Modifying the current system is necessary because the equivalent dose rate in the NBI room after reactor shutdown is higher than the design limit for radiation workers. The NBI maintenance concept is based on full-remote maintenance. There are, however, some problems that must be solved before full-remote maintenance could be realized—such as connection and disconnection of the electric power cables and complicated coolant pipes, and location of the maintenance equipment—this concept solves the aforementioned problem by enabling worker accessibility to the outside of the injector. The following design points are suggested to reduce the equivalent dose rate. The vacuum vessel should be composed of aluminum to reduce the induced radioactivity. Polyethylene, which has high shielding ability for neutrons, should be installed between the vessel and magnetic shield located outside the vacuum vessel to reduce not only neutron flux coming to the magnetic shield but also gamma-ray flux, caused by in-vessel components, leaking to the NBI room. The equivalent dose rate in the NBI room 1 week after reactor shutdown can be reduced to 28 µSv/h by applying the foregoing measures. Thus, the prospect exists for realizing access to the outside of the injector.