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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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Fusion Science and Technology
Latest News
Webinar: MC&A and safety in advanced reactors in focus
Towell
Russell
Prasad
The American Nuclear Society’s Nuclear Nonproliferation Policy Division recently hosted a webinar on updating material control and accounting (MC&A) and security regulations for the evolving field of advanced reactors.
Moderator Shikha Prasad (CEO, Srijan LLC) was joined by two presenters, John Russell and Lester Towell, who looked at how regulations that were historically developed for traditional light water reactors will apply to the next generation of nuclear technology and what changes need to be made.
Hemant Kumar, K. V. Phani Prabhakar, Shiju Sam, S. K. Albert, G. Padmanabham, A. K. Bhaduri, T. Jayakumar, E. Rajendra Kumar
Fusion Science and Technology | Volume 66 | Number 1 | July-August 2014 | Pages 192-199
Technical Paper | doi.org/10.13182/FST13-747
Articles are hosted by Taylor and Francis Online.
Laser and laser hybrid welding are among the processes chosen for joining Indian reduced activation ferritic martensitic (INRAFM) steel that will be used for fabrication of Indian test blanket modules (TBMs) to be tested in ITER. In the present study, a 3.5 kW slab CO2 laser in autogenous mode and hybridized mode with MIG were successfully employed to make butt joints in plates 6 mm and 12 mm thick respectively. Initially, bead-on-plate (BOP) experiments were conducted to study the effect of various laser and laser hybrid welding parameters such as laser power, welding speed, MIG torch angle, wire feed rate, composition of torch gas, gas shielding arrangement, stand off, distance between arc and laser, and focal position of the laser with respect to the surface. The resultant weld beads were evaluated for weld penetration, width of the weld, and width of the HAZ. Based on BOP welding studies, parameters were chosen for carrying out butt welding experiments using square butt for 6 mm plates and Y-groove edged configurations for 12 mm thick plates with various root face heights and included angles. The radiography results showed that all the welds were acceptable as per ASME Section III. The welds were also evaluated using hardness tests, metallographic analysis, and tensile, bend, and impact tests.