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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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Fusion Science and Technology
Latest News
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.
Rajendra Prashad Anand, Tejen Kumar Basu, Damaraju V. S. Ramakrishna
Fusion Science and Technology | Volume 31 | Number 3 | May 1997 | Pages 370-377
Technical Paper | Blanket Engineering | doi.org/10.13182/FST97-A30839
Articles are hosted by Taylor and Francis Online.
Uranium-233 breeding studies are carried out in a compact thorium-oxide cylindrical blanket assembly surrounded by a thick polypropylene reflector in a fusion neutron environment. The assembly consists of 11 rings of thorium-oxide rods stacked in a hexagonal geometry with a central through channel for the 14-MeV (d, t) neutron source. A total of 120 thorium-oxide probes are inserted inside the rods in different axial and radial locations in the assembly, which is then subjected to 14-MeV neutron irradiation for 25 h. Protactinium-233 gamma activity produced in the probes because of neutron captures in the thorium is measured using a high-efficiency, high-purity germanium detector. The measured 233U production rates are fitted to obtain axial and radial distributions for different rings. These distributions are used to obtain the total 233U breeding in the whole assembly. The integral measured values are found to be in good agreement with the calculated values obtained employing the MCNP Monte Carlo code using the BMCCS2 cross-section library.
