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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.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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
From the pages of Nuclear News: Industry update September 2024
Here is a recap of industry happenings from the recent past:
BWXT advanced nuclear reactor agreement signed
Burns & McDonnell, a family of construction and design companies, has entered into an agreement with BWX Technologies to further advance the design and development of the BWXT BANR microreactor, which has a “passively safe design” for powering remote facilities while providing a carbon-free source of heat and electricity. The two companies completed the first phase of their collaboration in early 2024 and intend to complete the second phase by the third quarter of 2025. Burns & McDonnell is helping BWXT develop the balance-of-plant systems for the BANR, generate the power plant layout, and perform preconstruction planning. Its scope of work also includes developing power cycle architecture, identifying critical components, integrating site design, and supporting steam and power distribution infrastructure and reactor building structures. The Wyoming Energy Authority is currently evaluating the feasibility of using the BANR in a state nuclear market for baseload heat and power deployed for remote industrial users, such as mining operations.
Craig E. Peterson, V. K. (Bindi) Chexal, Talmage B. Clements
Nuclear Technology | Volume 70 | Number 1 | July 1985 | Pages 104-110
Technical Paper | Third International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33668
Articles are hosted by Taylor and Francis Online.
The RETRAN-02 computer code was used to perform a best-estimate analysis of a 7.52-cm-diam hot-leg break in a three-loop Westinghouse pressurized water reactor. This break size produced a net primary coolant mass depletion through the early portion of the transient. The primary system started to refill only after the accumulator valves opened. As the primary system refilled, there were extreme temperature differentials around the system with cold, denser fluid collecting at the lower elevations and two-phase fluid at higher elevations.