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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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
Digital control system installed at China’s Linglong One
Earlier this month, the first digital control system was put in place at Linglong One, a small modular reactor demonstration project being built at the Changjiang nuclear power plant in Hainan Province. This is the world’s first land-based commercial SMR and is controlled by China National Nuclear Power Co. Ltd., a subsidiary of the China National Nuclear Corporation (CNNC).
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.
