ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
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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Nuclear Science and Engineering
April 2024
Nuclear Technology
Fusion Science and Technology
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?
Lucas P. Tucker, Shoaib Usman, Ayodeji Alajo
Nuclear Technology | Volume 194 | Number 1 | April 2016 | Pages 97-110
Technical Paper | doi.org/10.13182/NT15-67
Articles are hosted by Taylor and Francis Online.
The Missouri University of Science and Technology Subcritical Assembly has been brought back into service and upgraded with a new neutron detection system and Internet accessibility. Before the upgrade, neutron counting was possible in only one location. Using a movable detection system housed in acrylic tubes, measurements can now be taken in any empty fuel location and at any height within the tube, making three-dimensional flux mapping possible. By connecting the new detection system to a Canberra Lynx Digital Signal Analyzer, remote users can have limited data-collecting capabilities. To further enhance the potential of the facility, a Monte Carlo N-Particle transport code (MCNP) model of the subcritical assembly was created and validated by comparing its simulated predictions to experiments conducted at the facility. An approach to the criticality experiment using the 1/M approximation showed that the MCNP model accurately predicts keff if the detectors are placed between 27 and 36 cm from the neutron source. The results of an axial flux measurement experiment taken 20.3 cm from the neutron source differed from the MCNP-simulated results by an average of 12%. Finally, the validated MCNP model was used to show the effect of removing the facility’s fixed detector tube and redistributing its fuel. MCNP simulation predicts that the new configuration would increase the multiplication factor from 0.73481 ± 0.00008 to 0.76844 ± 0.00004.