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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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Latest News
Canada clears Darlington to produce Lu-177 and Y-90
The Canadian Nuclear Safety Commission has amended Ontario Power Generation’s power reactor operating license for Darlington nuclear power plant to authorize the production of the medical radioisotopes lutetium-177 and yttrium-90.
Suk-Kwon Kim, Bong Guen Hong, Dong Won Lee, Do Heon Kim, Young-Ouk Lee
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 746-750
Nuclear Analysis | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST09-A8998
Articles are hosted by Taylor and Francis Online.
A system analysis has been performed to develop the concepts for a fusion reactor and to identify the design parameters by using the tokamak system analysis code at KAERI (Korea Atomic Energy Research Institute). The system code elucidates the device parameters which satisfy the plasma physics and engineering constraints by taking into account a wide range of plasma physics and technology effects, simultaneously. The calculation of 1-D neutronic system code was coupled with this tokamak system code to optimize the reactor parameters. The numerical simulation for blanket neutronics was performed with MCNP5 code to calculate the tritium breeding ratios and neutron multiplications, which were the input parameter of system code. With the coupled system analysis and one-dimensional neutronic calculation, we assessed various types of DEMO blanket concepts with the requirements for the DEMO selected as to demonstrate the tritium self-sufficiency, to generate a net electricity amount, and for a steady-state operation.