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.
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.
Utility Working Conference and Vendor Technology Expo
August 8–11, 2021
Marco Island, FL|JW Marriott Marco Island
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Nuclear Science and Engineering
Fusion Science and Technology
New polls show substantial support for nuclear energy
Sixty percent of respondents in a recent national survey favored the use of nuclear energy, with only 25 percent opposing its use. While the latest Bisconti Research poll focuses on nuclear power and electricity generation, its findings on public interest in climate change and using a spectrum of sources to meet energy needs are consistent with a recent Pew Research Center poll on a broad set of energy policy and climate change topics. The approaches the two online surveys took to measuring public opinion on nuclear energy yielded different numbers but found some common ground.
B. Smith, P. Wilson, M. Sawan, T. Bohm
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 57-62
ITER | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | dx.doi.org/10.13182/FST09-A8876
Articles are hosted by Taylor and Francis Online.
Radiation shielding, thermal protection, and energy removal for ITER are provided by an array of firstwall/shield modules (FWS). Nuclear analysis of the shield modules is important for understanding their performance and lifetime in the system. Using Direct Accelerated Geometry (DAG)-MCNPX, a coupling of traditional MCNPX with the Common Geometry Module (CGM) and the Mesh Oriented dAtaBase (MOAB) developed at UW, high-fidelity 3-D neutronics analysis is now possible. Particles are transported in the CAD geometry reducing analysis time, eliminating input error, and preserving geometric detail. The surface source read-write capability that exists in MCNPX has been used in DAG-MCNPX to combine realistic source conditions with an efficient analysis model. A surface source was written using a 3-D model of ITER with a detailed plasma source. The surface source was then used in a detailed 3-D CAD model of Module 13.3-D high fidelity mesh tallies were used to calculate nuclear heating used in thermal-hydraulics analysis. Surface source results were compared against results using a hybrid 1-D/3-D approach in which a uniform neutron source is extended infinitely in the vertical direction. Results show that the hybrid source overestimated the total number and under estimated the average energy of particles incident on the FW. The hybrid approach was found to overestimate the nuclear heating at the front of the first wall by as much as 63%.