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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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Latest News
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
Sandro Sandri, Dan Gabriel Cepraga, Sergio Ciattaglia, Gilio Cambi
Fusion Science and Technology | Volume 26 | Number 3 | November 1994 | Pages 978-982
Tritium Technology, Safety, Environment, and Remote Maintenance | Proceedings of the Eleventh Topical Meeting on the Technology of Fusion Energy New Orleans, Louisiana June 19-23, 1994 | doi.org/10.13182/FST94-A40281
Articles are hosted by Taylor and Francis Online.
In this paper a preliminary evaluation of the Occupational Radiation Exposure (ORE) of the personnel involved in working activities on sections of the ITER primary cooling systems (PCS) is presented. The analysis has been restricted to the primary cooling circuits of the first wall (FW) and of the shielding blanket (SB). The radioisotopes produced by activation in the pipe's material surfaces are identified using the available works and data, their amount is obtained with suitable computer codes. The calculation is performed using the combination of a 1-D discrete ordinate code and activation codes. The corrosion/erosion problem is faced with two different approaches: a simplified model with steady state conditions and a computer code that evaluates the non-homogeneous distribution of the activated corrosion products (ACP) in the cooling circuit. The ORE is assessed for some working activities considering the direct irradiation from the ACP and the average distance of the workers from the cooling circuit. The results presented in the paper are useful in order to address experiments needed to evaluate the main unknown parameters for the ACP evaluation and then to design the primary cooling circuits. Furthermore the work outlines a methodological procedure and presents some preliminary results for the ORE assessment at the PCS of a fusion plant like ITER.