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Division Spotlight
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.
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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Nuclear Technology
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.
P. V. Subhash, Gunjan Indauliya, T. Sai Chaitanya, Priti Kanth, S. Jakhar, Sanjeev Varshney, Siddharth Kumar, Raja Krishna, Nirav Bhaliya, Sapna Mishra, P. Shrishail, Vinay Kumar
Fusion Science and Technology | Volume 71 | Number 2 | February 2017 | Pages 215-224
Technical Note | doi.org/10.13182/FST16-241
Articles are hosted by Taylor and Francis Online.
Activation and radioactive waste analysis has been carried out for an X-ray crystal survey spectrometer (XRCS) sight tube, which will be installed in equatorial port No. 11 assigned for the ITER diagnostics. The neutron transport calculations are performed using the Monte Carlo N-Particle code (MCNP). The base C-Lite neutronics ITER model is grossly modified to include all required details of the port plug, diagnostic apertures, and diagnostic system. The transport results provide neutron flux at desired positions. The sight tube is supposed to be placed in the interspace, after the closure plate, to channel X-rays to the spectrometer. Complete radioactive inventory calculations along with contact doses and nuclear activity levels are obtained for two different kinds of sight tube material. FISPACT-2007, an inventory code, is used for this purpose. The analysis for this particular sight tube can be used to obtain a material preference based on a radiation point of view. Further, the dependence of neutron spectrum and irradiation time on activity levels, contact dose rate, and production of dominant dose contributing radionuclides has been studied. Dominant radionuclides that contribute up to 95% of the total dose are identified, and their pathways are generated to back trace their sources as an effort to reduce the dose rate. The effect of reducing the cobalt content in SS316L(N)-IG on the contact dose rate is evaluated separately for the sight tube of the XRCS system. Many of the FISPACT calculations are repeated with ACTYS, a locally developed activation solver.
