ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
2022 ANS Winter Meeting and Technology Expo
November 13–17, 2022
Phoenix, AZ|Arizona Grand Resort
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!
Latest Magazine Issues
Sep 2022
Jul 2022
Latest Journal Issues
Nuclear Science and Engineering
October 2022
Nuclear Technology
Fusion Science and Technology
Latest News
CNSC vendor design review of eVinci microreactor to begin
Westinghouse's eVinci microreactor (Image: Westinghouse)
Westinghouse Electric Company has signed a service agreement with the Canadian Nuclear Safety Commission (CNSC) to bring the eVinci microreactor closer to commercialization, the company announced Tuesday. The agreement initiates a vendor design review (VDR)—a prelicensing technical assessment of a company’s reactor technology.
The objective of a VDR, according to the CNSC, is to verify the acceptability of a nuclear power plant design with respect to Canadian nuclear regulatory requirements and expectations, as well as Canadian codes and standards. The review also aims to identify fundamental barriers to licensing a new design in Canada and to assure that a resolution path exists for any design issues identified.
D. R. Patel, T. Koyanagi
Fusion Science and Technology | Volume 75 | Number 7 | October 2019 | Pages 636-641
Technical Paper | dx.doi.org/10.1080/15361055.2019.1647029
Articles are hosted by Taylor and Francis Online.
Silicon carbide (SiC) fiber–reinforced SiC matrix (SiC/SiC) composites have been widely investigated for potential fusion reactor applications. In this present investigation, the high-temperature creep performance of five types of SiC fibers is evaluated and microstructural analysis is performed. The creep behavior of the fibers was assessed by the bend stress relaxation method at various applied strains at 1500°C and 1700°C. The fibers tested include developmental-grade fibers with different residual silicon amounts (~0%, 2% to 3%, and 5% to 6%) fabricated by laser chemical vapor deposition at Free Form Fibers. Generally, the creep behavior of the Free Form (FF) fibers was similar to Hi-Nicalon Type S and/Tyranno-SA SiC fibers currently used for fabrication of SiC/SiC composites for fusion applications. However, all FF fibers exhibited the formation of pores after the creep tests at 1700°C regardless of residual silicon amount, which can be improved by further development via optimization of the composition and microstructure.
