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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Jun 2025
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Nuclear Science and Engineering
July 2025
Nuclear Technology
Fusion Science and Technology
Latest News
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.
Daniel A. Mattes, Da?istan ?ahin (NIST)
Proceedings | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technolgies (NPIC&HMIT 2019) | Orlando, FL, February 9-14, 2019 | Pages 733-735
Three gaseous effluent monitor systems collect air within the National Bureau of Standards Reactor (NBSR) confinement building. The normal air channel measures air sampled from the normal air, process room air, and emergency ventilation systems. The irradiated air channel measures air sampled from the irradiated air, confinement hoods, and emergency recirculating systems. All the collected air is combined and re-measured by the stack channels. Each of these channels provides radiation alarms and protective safety actions. Furthermore, these systems provide redundant protection against personnel exposure and uncontrolled release of radioactive material to the environment. The normal air channel continuously monitors the exhaust air leaving the building for gaseous radioactive release. A vacuum pump draws air, from a sample tap in the normal air duct downstream of the HEPA filters, through a shielded detector chamber. The existing analog system utilizes a Geiger-Mueller probe sensitive to the beta-gamma radiation emitted by the gaseous airborne radioactivity (predominately AR-41). A pre-amplifier connects the detector to the counting circuits in the log-count ratemeter. The ratemeter has alarm outputs that actuate the major scram circuits and the annunciator system. The building exhaust activity high alarm alerts the reactor operator to a high activity condition in the normal air monitoring system. The new system selected to replace the normal air channel is comprised of a digital ratemeter and scintillation detector which, based on the company provided documentation, has been through a rigorous analysis for use in safety-related nuclear systems. As utilized at the NBSR, the unit does not have digital communication and is used for its intended purpose without modification to the ratemeter. The digital unit does not change how the design function of the normal air channel is performed, i.e. the new unit measures radioactive isotope concentrations in the gas samples using a radiation detector. The new radiation detector is similar with regards to radiation detection capabilities and has a greater dose rate range capability compared to the existing detector. A detailed assessment of existing and the new detector capabilities was conducted to identify differences. The most significant deviation was that the new normal air monitoring channel introduces a digital logic for the quantification of radiation levels. The use of digital equipment (hardware and software) therefore has the potential of creating a new type of malfunction that was not previously considered and needed to be analyzed to determine the impact on the pertinent design functions as a safety system.