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Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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February 2024
Latest News
Can hydrogen be the transportation fuel in an otherwise nuclear economy?
Let’s face it: The global economy should be powered primarily by nuclear power. And it probably will by the end of this century, with a still-significant assist from renewables and hydro. Once nuclear systems are dominant, the costs come down to where gas is now; and when carbon emissions are reduced to a small portion of their present state, it will become obvious that most other sources are only good in niche settings. I mean, why use small modular reactors to load-follow when they can just produce that power instead of buffering it?
Dong Won Lee, Hyung Gon Jin, Eo Hwak Lee, Jae Sung Yoon, Suk Kwon Kim, Seungyon Cho, Hyun Gon Lee
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 680-683
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-979
Articles are hosted by Taylor and Francis Online.
A hypervapotron mockup was fabricated and used in the Neutral Beam Injection (NBI) heating system at KAERI. During the test, especially with the JAEA ion source, which has a focused beam and a long pulse, some failures in the mockup were experienced. Using the existing correlation for a critical heat flux (CHF), the incident CHF was assessed, in which the modified Tong-75 CHF correlation for the one-sided heat flux was used. In addition, using the conventional CFD and FEM codes such as ANASYS-CFX and ANYS-mechanical, the thermal lifetimes were evaluated according to the beam operation and water cooling conditions. The evaluated ICHF is 28.6 MW/m2 and is much higher than the loaded peak heat of about 8.7 MW/m2 at a 2.3 MW heat load. The cause of failure seems not to be the CHF considering the existing correlations. The thermal lifetimes were evaluated to be about 100 cycles and 11 cycles for 1.56 MW and 2.3 MW heat load conditions, respectively. When the dump heat is reached in the mockup frequently, it can fail in the corner of the inlet region below 11 cycles when a 2.3 MW heat is loaded.