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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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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Latest News
WIPP improves utility shaft safety, begins infrastructure project
Harrison Western Shaft Sinkers (HWSS), the company drilling a new utility shaft at the Department of Energy’s Waste Isolation Pilot Plant in New Mexico, has retained a safety culture expert following a near-miss accident in the shaft late last year. The safety expert will conduct monthly facilitated discussions with crews working on the shaft to reinforce expectations for identifying concerns regarding unsafe circumstances, according to a recent report by the Defense Nuclear Facilities Safety Board (DNFSB).
Xin-Guo Yu, Ki-Yong Choi, Chul-Hwa Song, Istvan Trosztel, Ivan Toth, Gyorgy Ezsol
Nuclear Technology | Volume 191 | Number 2 | August 2015 | Pages 136-150
Technical Paper | Reactor Safety | doi.org/10.13182/NT14-55
Articles are hosted by Taylor and Francis Online.
Pressure waves might be expected in a nuclear reactor system due to a sudden rupture of a pipe or to quick opening or closure of a system valve. Once generated, they can result in large mechanical loads on the reactor pressure vessel internal structures and pipelines, threatening their integrity. This kind of phenomenon is an important issue and a limiting accident case for nuclear power plant safety, which requires an extensive analysis to ensure plant safety. To study these phenomena, four pressure wave propagation (PWP) tests have been performed in the PMK-2 test facility in MTA-EK. In addition, the first one of the four tests has been used to assess the capability of the MARS-KS code in simulating PWP phenomena. Then, an input model representing the PMK-2 test facility was developed to simulate the tests. Herein, the MARS-KS code simulation results are compared with the test results for the first PWP test. The comparison shows that the MARS-KS code can simulate the PWP frequencies and pressure wave peaks well. After this qualified assessment, the MARS-KS code is then deployed to conduct a sensitivity analysis on the effect of the break size, break opening times, initial coolant conditions, and existence of the pressurizer on the PWP phenomena. The sensitivity analysis on the break opening times shows that the pressure wave amplitude is relevant to the break opening times and that the shorter the break opening time is, the faster the pressure depressurizes. The sensitivity analysis on the effect of the break sizes shows that the larger the break size is, the higher the pressure peak is. And, there is little effect of initial coolant pressure and temperatures and isolation of the pressurizer.