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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.
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2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC 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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Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Argonne investigates industrial SMR applications for postwar Ukraine
Argonne National Laboratory will play a leading role in planning and rebuilding a nuclear-generated clean energy infrastructure for postwar Ukraine as part of the lab’s focus on developing small modular reactor applications to help countries meet energy security goals. The latest plans, described in a November 19 article, were announced on November 16 at COP29 in Baku, Azerbaijan.
B. A. Kalin, A. N. Suchkov, V. T. Fedotov, O. N. Sevryukov, P. V. Morokhov, V. M. Ananiyn, A. A. Ivannikov, A. A. Polyansky, I. V. Mazul, A. N. Makhankov, A. A. Gervash
Fusion Science and Technology | Volume 65 | Number 2 | March-April 2014 | Pages 212-221
Technical Paper | doi.org/10.13182/FST13-667
Articles are hosted by Taylor and Francis Online.
As applied to the manufacture of the ITER first wall, a rapidly quenched copper-based filler metal for brazing chromium-zirconium copper alloy (CuCrZr) with beryllium (Be) at temperatures below 720°C has been selected. The composition of the given filler metal has been optimized by varying the concentration of alloying elements, such as Sn, Ni, and P, improving the filler functional properties and quality. Rapidly quenched ribbon-type filler metals with various contents of alloying elements were investigated by differential thermal and X-ray phase analysis, atomic force microscopy, and scanning electron microscopy. To improve the casting performance of the filler metal and obtain high-quality ribbons, the kinematic viscosity of brazing alloys with various contents of Ni, Sn, and P has been investigated. The chromium-zirconium copper alloy has been brazed with Be using the filler metals obtained (by furnace brazing and fast brazing by passing an electric current). Based on the results of complex research, an ultrafast (quenching rate of ∼105°C/s) quenched brazing alloy STEMET 1101M (Cu-9.1Ni-3.6Sn-8.0P, in weight percent) has been selected and manufactured in the form of a ribbon that is 50 mm in width and 50 μm in thickness. An experimental mock-up of the ITER first wall has been made in D.V. Efremov SRIEA by rapid brazing (by passing a current) using the filler metal STEMET 1101M. The brazed joint has withstood 15 000 cycles of thermocycling under a thermal load of 0.5 to 5.9 MW/m2 without breaking.
