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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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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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
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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
M. Wykes
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 39-42
Technical Paper | Tritium Science and Technology - Tritium Processing, Transportation, and Storage | doi.org/10.13182/FST05-A875
Articles are hosted by Taylor and Francis Online.
The tritium inventory of all the ITER torus cryopumps open to the vacuum vessel has an administrative limit of 120 g, including tritium bound to hydrocarbon compounds formed by combination of fuel gas with carbon plasma-facing components. The total hydrogenic inventory of each of the torus cryopumps has to be less than that resulting in a deflagration pressure of 0.2 MPa (the design pressure of the ITER vacuum vessel of which the torus and neutral beam cryopump pressure boundaries are a part) following a hydrogen-air ignition. Since the neutral beamline fuelling is with protium and deuterium only, these pumps do not significantly contribute to the 120 g tritium limit. The hydrogenic inventories of both the torus and neutral beam cryopumps add to the total for the vacuum vessel following an in-vessel ingress of coolant from a failed water-cooled component, wherein hydrogen is produced from steam reacting with hot metallic dust. There is therefore a large incentive to keep the peak inventories of both the torus and neutral beamline cryopumps as low as practicable. The paper describes the regeneration patterns of the torus and neutral beamline cryopumps that are used to attain this goal while achieving the required vacuum conditions commensurate with the reference ITER pulse scenarios.