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
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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
Mar 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
April 2024
Nuclear Technology
Fusion Science and Technology
February 2024
Latest News
Direct waste transfer process quickens at Savannah River Site
The Department of Energy Office of Environmental Management’s liquid waste contractor at the Savannah River Site this month marked the first direct transfer of decontaminated waste from the Salt Waste Processing Facility (SWPF) to the Saltstone Production Facility (SPF). This is a new step in optimizing waste processing, according to the DOE.
Wei Xu, Jianhua Xia, Xiaojing Liu, Xu Cheng, Wei Zeng
Nuclear Technology | Volume 205 | Number 1 | January-February 2019 | Pages 281-296
Technical Paper | doi.org/10.1080/00295450.2018.1457887
Articles are hosted by Taylor and Francis Online.
Bottom reflooding is the third phase when a large-break loss-of-coolant accident occurs. Due to the complexity and importance, especially in a distinct narrow rectangular channel, various research methods can be utilized to understand the whole process. Test facility is established to figure out the thermal-hydraulic behaviors during bottom reflooding, and the acquisition of accurate solid temperature is essential. The inverse heat transfer problem method is applied to take full advantage of experimental data. In addition, a bottom reflooding transient (BRT) code is utilized to calculate various parameters conveniently. A three-dimensional heat conduction equation for a transient state is solved implicitly to obtain solid temperature distribution, surface heat flux, and heat transfer coefficient at the cooling surface. The simulation results of the BRT code are compared with that of RELAP5, an available system code, and the experimental results. A conclusion that can be derived is that the BRT code shows good applicability of simulating bottom reflooding in a narrow rectangular channel.