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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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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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.
Ian J. Hastings, David R. McCracken, Elio Mizzan, Roger D. Barrand, John R. Kelm, Ken E. Nash, J. Novak
Nuclear Technology | Volume 70 | Number 2 | August 1985 | Pages 268-273
Technical Paper | Material | doi.org/10.13182/NT85-A33652
Articles are hosted by Taylor and Francis Online.
Twenty-four-hour sweep tests have been carried out in flowing air at 200 and 400°C on deliberately defected UO2 fuel elements with 2.5-yr discharge times. At 200 C there was no diametral change, but at 400 °C, swelling and severe sheath cracking were observed. Neither short-lived fission products nor 134Cs, I37Cs, or 106Ru were detected above background. Maximum 85Kr release was ≤7.4 × 104 Bq (≤2 × 10-6 Ci).