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The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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.
M. Bradbury, R. Ratnayake (NuScale Power)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 165-171
Data from Critical Heat Flux (CHF) and Critical Power (CP) tests are used for developing CHF and CP (or dryout) correlations to predict the maximum allowable heat flux at points of operational interest. CHF and CP tests are conducted using heater rod arrays representing fuel rods in a partial fuel bundle. Heat is directly generated in these heater rods depicting the axial power distributions of interest. The test rod array is housed in a slender vertical channel of metallic walls that are generally unheated. During testing, part of the heat generated in the heater rods is lost to the environment through the channel walls. Heat loss through the channel wall has the potential to favor channel thermal-hydraulic (T-H) conditions, and thereby make power measurements non-conservative. Typically, a single conservative estimate of the heat loss obtained from a separate isothermal test of the same test configuration is used regardless of the reactor conditions tested during a test campaign. This paper investigates the basis for the use of a single value for channel heat loss under varying reactor conditions. Results indicate that this practice has sound bases when applied with appropriate conservatisms.