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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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Kentucky legislature sends nuclear bills to governor
Kentucky’s Republican-majority legislature passed a bill this past week that could bring nuclear energy to the “coal-is-king” state as lawmakers broadly seek solutions to reduce carbon emissions. The bill went to Democratic Gov. Andrew Beshear on Monday for final approval.
Heimo Bürbaumer, Gerald Kamelander
Fusion Science and Technology | Volume 37 | Number 2 | March 2000 | Pages 131-145
Technical Paper | doi.org/10.13182/FST00-A129
Articles are hosted by Taylor and Francis Online.
The temporal evolution of the operating point of a fusion plasma during the ignition access, during ignited and subignited operation phases, is analyzed for plasmas like that of the International Thermonuclear Experimental Reactor (ITER) on the basis of a one-half-dimensional set of equations including feedback equations for auxiliary heating and fuel supply. It is shown that simple proportional feedback controls do not work taking into account the delay times in the control process. Proportional-integral-differential (PID) and improved types of control are examined for the purpose of controlling a fusion plasma against sudden parameter changes. On this basis a study on the simultaneous use of D-T fuel injection and auxiliary heating control methods for an ITER-like plasma is carried out, resulting in an algorithm capable of finding the optimal operation point in the ignited regime or a high-Q operating point in a subignited case taking into account density and beta limits and stabilizing the reactor performance against changes in confinement.