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
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.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Jan 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
February 2025
Nuclear Technology
January 2025
Fusion Science and Technology
Latest News
Uranium spot price closes out 2024 at $72.63/lb
The uranium market closed out 2024 with a spot price of $72.63 per pound and a long-term price of $80.50 per pound, according to global uranium provider Cameco.
Chun-Sheng Chien, Shih-Jen Wang, Show-Chyuan Chiang
Nuclear Technology | Volume 161 | Number 3 | March 2008 | Pages 203-209
Technical Paper | Reactor Safety | doi.org/10.13182/NT08-A3923
Articles are hosted by Taylor and Francis Online.
The MAAP4 code is a fast-running severe accident analysis and management code widely used in nuclear industrial applications. It has been used as a severe accident analysis tool with which the timing of key events and source terms in the accident are assessed in Taiwan for many years. In the case of a loss-of-coolant accident (LOCA), it needs to know its break area and break elevation prior to reconstructing the accident for further analysis. For the system with more than one unknown parameter, it is not easy to identify these parameters since their tuning work becomes sophisticated.The purpose of this paper is to find a better solution for this problem by coupling an optimization module with the MAAP4 simulation code. In this paper, a recirculation line break LOCA of the Kuosheng nuclear power plant is cited as a reference case. Different recirculation line break areas are tested and verified. This optimization module coupled with the MAAP4 code can be used to identify the break elevation and area if the shroud water level drops below the break point.