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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
Sung Nam Lee, Nam-Il Tak
Fusion Science and Technology | Volume 76 | Number 3 | April 2020 | Pages 238-245
Technical Paper | doi.org/10.1080/15361055.2019.1705725
Articles are hosted by Taylor and Francis Online.
The High-Temperature Gas-cooled Reactor (HTGR) has been selected as one of the next-generation nuclear power plants because of its passive safety features. The Korea Atomic Energy Research Institute (KAERI) has been studying how to utilize HTGR efficiently and safely. The HTGR uses graphite as a moderator and helium as a coolant. Once tritium is produced, it is released into the coolant; once released from the core, tritium travels within the primary loop. Because the coolant is gas phase, it is easy to transport to other systems. While it circulates in the primary loop, tritium is involved in processes that include leakage, purification, and permeation. KAERI has been developing a tritium behavior analysis code named TRitium Overall Phenomena analYsis (TROPY) to analyze tritium transport and predict the amount of tritium in the loop in the HTGR core. In this paper, the functions of the TROPY code are introduced, and the amount of tritium in each loop and the amount released into the product hydrogen from the MHTGR 350-MW(thermal) core are explained.