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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
R. J. Price
Nuclear Technology | Volume 16 | Number 3 | December 1972 | Pages 536-542
Technical Paper | Material | doi.org/10.13182/NT72-A31222
Articles are hosted by Taylor and Francis Online.
Hot-pressed α-silicon carbide temperature monitors were irradiated at 525 and 772°C to 4.8 × 1021 n/cm2 (E > 0.18 MeV). Postirradiation isochronal annealing was carried out for 1-h periods at either 25 or 50°C intervals between 300°C and 1200 to 1500°C. Above the irradiation temperature the sample length decreased linearly with annealing temperature, while the electrical resistivity increased exponentially with temperature. Straight lines were fitted through the length-versus-temperature and log (resistivity)-versus-temperature data points and the temperature, T1 at which the line intersected the as-irradiated base line was measured. For both length change and resistivity, mean values of T1 agreed with the measured irradiation temperature within experimental accuracy. The precision of a single determination of T1 was obtained from curve-fitting statistics and was about ±20°C for irradiation at 525°C and ±30 at 772°C (90% confidence limits) for both length and resistivity measurements. The sample-to-sample reproducibility of T1 was estimated from the standard deviation of four repeated measurements and was similar to the precision of a single determination.