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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Fusion Science and Technology
Latest News
Former Exelon CEO Chris Crane remembered for “transformational milestones”
Crane
Exelon announced that Chris Crane, the company’s former chief executive, passed away on Saturday in Chicago at the age of 65.
Crane served as the company’s president and CEO from 2012 until his retirement in December 2022. During his tenure, he steered the energy company through several transformational milestones, including the successful mergers with Constellation Energy in 2012 and Pepco Holdings in 2016, creating the largest utility business by customer count in the United States.
In 2022, with the spin-off of Constellation as the generation and retail side of energy business (with the largest U.S. nuclear fleet), Crane led the creation of a stand-alone transmission and delivery energy company.
G. Casini
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 1228-1232
Blanket and First Wall Engineering | doi.org/10.13182/FST83-A23025
Articles are hosted by Taylor and Francis Online.
A review of the experimental and conceptual design work in progress at JRC-Ispra to investigate the feasibility of the eutectic Li17Pb83 as a liquid breeder for experimental power reactors is presented. Results of recent measurements to implement the data base of this material are given in the following areas: physical parameters, hydrogen solubility and recovery, chemical reactivity with air and water, compatibility with steel. The studies carried out on blanket concepts for the INTOR (International Tokamak Reactor)/NET (Next European Torus) projects are outlined and discussed.
