ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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!
Latest Magazine Issues
May 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
June 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Steam is a sign of cooling system function . . . at ITER
Steam from one of ITER’s ten induced-draft cooling cells offers visual confirmation of a successful cooling system test, the ITER organization announced April 30. ITER’s cooling system features 60 kilometers of piping with pumps, filters, and heat exchangers that can pull water through at up to 14 cubic meters per second. Once fully operational, two cooling loops—one to remove the heat generated by the plasma in the ITER tokamak and one for its supporting infrastructure—will be capable of extracting up to 1,200 MW of heat.
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.