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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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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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Latest News
Lightbridge announces first U-Zr fuel rod samples extruded at INL
Lightbridge Corporation announced today that it has reached “a critical milestone” in the development of its extruded solid fuel technology. Coupon samples using an alloy of zirconium and depleted uranium—not the high-assay low-enriched uranium (HALEU) that Lightbridge plans to use to manufacture its fuel for the commercial market—were extruded at Idaho National Laboratory’s Materials and Fuels Complex.
Isao Aoki, Satoshi Konishi, Ryouichi Kurihara, Yasunori Iwai, Masataka Nishi
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 835-839
Design and Model | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22702
Articles are hosted by Taylor and Francis Online.
The inherent delays in components of fuel processing subsystems of fusion reactor on the pulse operation were simulated to analyze the time dependent tritium inventory in the tritium storage with the time in the throughput capacity of the fuel processing to that required to satisfy pulse operation cycle repetition. The simulation results of inherent delays in components of fuel processing subsystems demonstrates that tritium inventory in the tritium storage is influenced by a cumulative time lag system responses on the pulse operation continuity even when adoption of duty cycle is sustained. To satisfy pulse operation up to long pulse specified the capacity of the fuel processing subsystems and tritium storage will need to be increased by a number of fuel storage beds. Variation with the time of tritium product from isotope separation subsystem determines the time dependent characteristic of tritium inventory in the tritium storage. Representative value defined by the inherent system responses provides an information of optimum condition of pulse operation campaign.