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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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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
V. G. Vasilyev
Fusion Science and Technology | Volume 8 | Number 2 | September 1985 | Pages 2149-2152
Blanket and Process Engineering | Proceedings of the Second National Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Dayton, Ohio, April 30 to May 2, 1985) | doi.org/10.13182/FST85-A24601
Articles are hosted by Taylor and Francis Online.
Lithium oxide is a potential solid-state blanket material for fusion applications. Equilibrium water vapour pressure in the system Li2O-H2O including dehydration LiOH H2O and dissociation LiOH were studied in a temperature range 70–160 and 270–440°C respectively. The kinetics of LiOH dissociation was studied in a range 390–450°C by Mak Ben quartz spring balance and in a range 450–600°C by volumetric method collecting hydrogen after chemical decomposition of water on hot metal. Kinetics of tritium oxide release from neutron irradiated lithium oxide with initial concentration 1,11 109 and 3,33 109 Bq/g was studied in vacuum 1,333 Pa in the range 280–450°C. The initial and final stages of the process are characterized by activation energies of 83,5 and 54,4 kJ/mol, respectively. Taking into account the formation of OT groups into inorganic compound under irradiation a mechanism of water and tritium oxide formation and recovery from solid phase is a chemical recombination reaction (polycondensation) which brings to the formation of H2O or HTO and inorganic polymer (sintering).