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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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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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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BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
Mohamed A. Abdou, Layton J. Wittenberg, Charles W. Maynard
Nuclear Technology | Volume 26 | Number 4 | August 1975 | Pages 400-419
Technical Paper | Reactor | doi.org/10.13182/NT75-A24441
Articles are hosted by Taylor and Francis Online.
Developing a controlled thermonuclear reactor blanket that minimizes lithium and tritium inventories is feasible. The tritium inventory is minimized by keeping the lithium inventory to a minimum and utilization of a lithium-bearing compound with low retention for tritium and an efficient tritium extraction system. The lithium inventory is minimized by employing a thin layer of 6Li operating in a soft neutron spectrum obtained by slowing down the deuterium-tritium (DT) neutrons in beryllium. Material properties and performance such as tritium retention, irradiation characteristics, and chemical compatibility of possible lithium-bearing materials and beryllium compounds have been evaluated. The blanket of the conceptual fusion reactor UWMAK-II uses stainless steel for first wall and structure, helium coolant, lithium aluminate enriched to 90% 6Li for tritium breeding, metallic beryllium for neutron multiplication and moderation, and graphite for reflection and additional neutron moderation. A breeding ratio of 1.18 and nuclear heating of 18 MeV per DT neutron are obtained. The lithium inventory is only 4 × 104 kg (40 Mg). The steady -state inventory of tritium in the breeder is only 40 g, which is more than two orders of magnitude lower than that in blankets using lithium for cooling and neutron moderation as well as tritium breeding. Tritium leakage to the steam is kept to ∼1 Ci/day by oxidation of the tritium in the helium coolant and absorption by a molecular sieve dessicant. Plant reliability is improved and accidental tritium and energy release are minimized in the type of blankets examined in this study.