ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
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.
Meeting Spotlight
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
Standards Program
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.
J. G. Carver
Nuclear Technology | Volume 6 | Number 6 | June 1969 | Pages 526-532
Technical Paper and Note | doi.org/10.13182/NT69-A28281
Articles are hosted by Taylor and Francis Online.
A pressurized subcritical facility was constructed with its main pressure vessel directly above a 28-in.-diam (71-cm) fission source plate centered on the top face of the General Electric Nuclear Test Reactor (NTR). The main pressure vessel had an inside diameter of 36 in. and inner length (less head) of 48 in. to accommodate light-water-moderated fuel lattices with a keff 0.98, constructed of low-enrichment oxide fuel rods. Maximum operating conditions for the facility were 540°F at 1050 psig. The system was heated electrically at 110 kW to raise the temperature and at 35 kW to maintain it at 540°F. With the NTR at 30 kW, and with lattice keff8 n/(cm2 sec) at lattice center. The facility has been used to carry out a program of measurements of nuclear reaction rates within H2O-moderated subcritical lattices of plutonium-enriched oxide fuel rods.