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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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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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.
V. B. Morozov, A. E. Kiselev, A. A. Kiselev, K. S. Dolganov, D. Yu. Tomashchik, S. N. Krasnoperov
Nuclear Technology | Volume 207 | Number 2 | February 2021 | Pages 204-216
Technical Paper | doi.org/10.1080/00295450.2020.1767998
Articles are hosted by Taylor and Francis Online.
This paper considers the issues of safety assessment of new nuclear power plant (NPP) projects with VVER Generation III+ reactors in relation to the probability target for large release, which is subject to verification in the development of a full-scale Probabilistic Safety Assessment (PSA) Level 2. The design solutions implemented in Generation III+ reactors allow reducing the probability of a severe accident (SA) due to internal initial events to a level of 10−7/year. Exceeding the radioactive release criterion may thus be related mainly to the consequences of beyond-design external events. This places special demands both for the selection of SA scenarios to consider and the methods for modeling the accident progression and consequences. The paper presents a method for selecting the representative SAs in the frame of PSA of new VVER NPP projects and a practical example of radiological analysis for two bounding accidents at an arbitrary NPP using an advanced integrated computer code system.