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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
Terrestrial Energy, Schneider partner on molten salt reactor
Terrestrial Energy and Schneider Electric are teaming to deploy Terrestrial Energy's integral molten salt reactor (IMSR) to provide zero-emission power to industrial facilities and large data centers.
The companies signed a memorandum of understanding in April to jointly develop commercial opportunities with high-energy users looking for reliable, affordable, and zero-carbon baseload supply. Terrestrial Energy said that working with Schneider “offers solutions to the major energy challenges faced by data center operators and many heavy industries operating a wide range of industrial processes such as hydrogen, ammonia, aluminum, and steel production.”
Chang An Chen, Xin Zhou, Zhanlei Wang, Bo Wang, Lingbo Liu, Xin Xiang, Yong Yao, Jiangfeng Song
Fusion Science and Technology | Volume 73 | Number 1 | January 2018 | Pages 34-42
Technical Note | doi.org/10.1080/15361055.2017.1368333
Articles are hosted by Taylor and Francis Online.
The Chinese (CN) Helium Cooled Ceramic Breeding (HCCB) Test Blanket Module (TBM) (CN HCCB TBM) set with its ancillary systems will demonstrate the feasibility of in-pile tritium production/breeding in ITER for fuel self-sufficiency and high-grade fusion energy conversion to heat and extraction for a future magnetic confined fusion reactor. Tritium release in some major components of the recently designed TBM systems through permeation and natural leakage was estimated with simple diffusion/permeation and leak rate calculation models. Results showed that because of the tritium permeation barrier coating for tritium confinement in some tritium containments, total tritium release to the environment by permeation in the CN HCCB TBM and ancillary systems will be kept well below 2 Ci/full-power day. However, tritium release through natural leakage from components can be neglected compared with permeation. Equipped with ITER tritium safety guarantee facilities like the tritium monitoring and detritiation systems, tritium release from CN TBM system–caused radiological safety issues will be well controlled.