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2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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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My Story: John L. Swanson—ANS member since 1978
. . . and in 2019, on his 90th birthday.
Swanson in 1951, the year of his college graduation . . .
My pre-college years were spent in a rural suburb of Tacoma, Wash. In 1947, I enrolled in Reed College, a small liberal arts school in Portland, Ore.; I majored in chemistry and graduated in 1951. While at Reed, I met and married a young lady with whom I would raise 3 children and spend the next 68 years of my life—almost all of them in Richland, Wash., where I still live.
I was fortunate to have a job each of my “college summers” that provided enough money to cover my college costs for the next year; I don’t think that is possible these days. My job was in the kitchen/dining hall of a salmon cannery in Alaska. Room and board were provided and the cannery was in an isolated location, so I could save almost every dollar of my salary.
Linjun Xie, Changxun Wang, Wei Zhang, Xin Shen, Minglei Hu, Chunhua Bian, Yilun Xu
Nuclear Science and Engineering | Volume 196 | Number 2 | February 2022 | Pages 221-233
Technical Note | doi.org/10.1080/00295639.2021.1964325
Articles are hosted by Taylor and Francis Online.
Nuclear power pipeline ice plug technology, as the main technical method of nuclear power safety maintenance and innovative design, plays a protective role in the long-term safe operation of nuclear power plants. During the ice plug process, pipelines have complex stress states, which can easily lead to problems such as material yielding, cracking, and even damage. In this study, by building an ice plug test platform for nuclear power pipelines, an ice plug test and a numerical analysis of nuclear power pipelines are carried out to explore the stress distribution of nuclear power pipelines during the ice plug process and its impact on the performance of pipeline materials and to analyze the safety of pipelines in the ice plug process. This study shows that the distribution of stress in the pipeline during ice plug is related to the temperature change and cooling rate of the pipe wall. The stress distribution in different parts is uneven, and the maximum stress appears near the edge of the jacket. According to the temperature data of the pipe wall, the stress distribution of the pipe wall can be obtained by the finite element method. From the test and finite element results, it can be seen that when the frost line length of the pipeline is less than 200 mm, the pipeline ice plug method is safe and feasible.