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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
C. Konno, F. Maekawa, Y. Ikeda, Y. Oyama, K. Kosako, H. Maekawa
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 2169-2173
Blanket Shield and Neutronic | doi.org/10.13182/FST92-A30041
Articles are hosted by Taylor and Francis Online.
A series of experiments concerning fusion reactor shielding have been initiated for next fusion devices such as ITER. At the first step the bulk shielding experiments using SS316 materials were performed. Two experimental assemblies were adopted; one was a cylindrical assembly of SS316 (1.2 m in diameter and 1.12 m in thickness) and was set at 0.3 m from the D-T neutron source (Experimental assembly #1), and the other surrounded the D-T neutron source by a source reflector of 0.2 m-thick SS316 adding to the experimental assembly #1 (Experimental assembly #2). Neutron spectra from a few keV to 1 MeV and above 2 MeV were measured at the positions from 0 to 0.91 m in depth using small proton recoil gas proportional counters and a 14 mm-diam. NE213 spectrometer, respectively. Gamma-ray spectra and heating rates were measured using a 40 mm-diam. NE213 spectrometer and TLD, respectively. As neutron spectrum indices, fission and activation reaction rates were measured by fission counters of 235U and 238U, and foils of Al, Ti, Fe, Co, Ni, Zr, Nb, In and Au, respectively. The lower energy neutrons increased more than a few times in the assembly #2 compared with those in the assembly #1 due to neutrons scattered by the source reflector. It is expected that the nuclear data and calculation codes used in nuclear design of fusion devices will be examined based on these experimental data.