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
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2023)
February 6–9, 2023
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 2023
Jul 2022
Latest Journal Issues
Nuclear Science and Engineering
February 2023
Nuclear Technology
Fusion Science and Technology
January 2023
Latest News
Nuclear energy: enabling production of food, fiber, hydrocarbon biofuels, and negative carbon emissions
In the 1960s, Alvin Weinberg at Oak Ridge National Laboratory initiated a series of studies on nuclear agro-industrial complexes1 to address the needs of the world’s growing population. Agriculture was a central component of these studies, as it must be. Much of the emphasis was on desalination of seawater to provide fresh water for irrigation of crops. Remarkable advances have lowered the cost of desalination to make that option viable in countries like Israel. Later studies2 asked the question, are there sufficient minerals (potassium, phosphorous, copper, nickel, etc.) to enable a prosperous global society assuming sufficient nuclear energy? The answer was a qualified “yes,” with the caveat that mineral resources will limit some technological options. These studies were defined by the characteristic of looking across agricultural and industrial sectors to address multiple challenges using nuclear energy.
Wen-Yu Wang, Yung-Shin Tseng, Chih-Hung Lin, Tsung-Kuang Yeh
Nuclear Technology | Volume 208 | Number 7 | July 2022 | Pages 1165-1183
Technical Paper | doi.org/10.1080/00295450.2021.2011576
Articles are hosted by Taylor and Francis Online.
One of the important criteria of the emergency planning (EP) exemption for nuclear power plant (NPP) decommissioning is a minimum of 10 h available before any spent nuclear fuel (SNF) cladding temperature reaches 900°C after a complete loss of the spent fuel pool (SFP) water inventory with no heat loss (adiabatic). This study used the computational fluid dynamics (CFD) code to analyze the cladding heatup time of the SFP for a boiling water reactor. First, the developed CFD local model of the SFP was compared with the U.S. Nuclear Regulatory Commission’s (NRC’s) report on SFP heatup calculations, NSIR-2015-001. The CFD results were similar to the theoretical calculations and MELCOR results for cases with and without racks. The results also indicated that racks can significantly delay the heatup time. This study also performed sensitivity studies to identify the effects of fuel burnup, hottest assembly, and fuel loading configurations. After validation of the CFD local model against MELCOR, a whole-pool CFD model of the Chinshan SFP was developed and successfully applied to analysis for the EP exemption of the Chinshan NPP. The results predicted using the whole-pool CFD model of the Chinshan SFP agreed well with the MELCOR results. Additionally, the required 900°C heatup times were calculated based on the actual decay heat of each cycle and fuel loading at the Chinshan SFP. The required 900°C heatup times were 19.1, 54, and 64.6 h for the Chinshan SFP at 1, 5, and 10 years after shutdown, respectively. The actual fuel loading and decay heat of the Chinshan SFP met the requirements for the EP exemption after 1 year of shutdown. The main purpose of this study is to demonstrate that the CFD code can be used as a tool to calculate SFP fuel assembly heatup times for the EP exemption. The advantage of using the CFD code instead of MELCOR is that the whole-pool SFP model can be developed based on the actual decay heat of each cycle and fuel loading and to determine more realistic fuel assembly heatup time for the EP exemption.
