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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
New laws offer nuclear industry incentives for existing power plant uprates
This year, the U.S. nuclear industry received a much-needed economic boost that could help preserve operating nuclear power plants and incentivize upgrades that extend their lifespan and power output.
Signed into law in 2022, the Inflation Reduction Act offers production tax credits (PTCs) for existing nuclear power plants and either PTCs or investment tax credits (ITCs) for new carbon-free generation. These credits could make power uprates—increasing the maximum power level at which a commercial plant may operate—a much more appealing option for utilities.
C. F. Bullinger, W. J. Kann
Nuclear Science and Engineering | Volume 3 | Number 4 | April 1958 | Pages 379-386
Technical Paper | doi.org/10.13182/NSE58-A25475
Articles are hosted by Taylor and Francis Online.
The control rod drive mechanisms installed on the Argonne Experimental Boiling Water Reactor (EBWR) are of an externally operated lead screw and nut type in which the control rod extension shafts are driven through pressure breakdown, collected leakage seals. The mechanisms which are located below the reactor are fabricated from conventional industrial materials, such as carbon steel, brass, cast iron, nylon, etc., and are lubricated with grease. They may be serviced during reactor operation, and are removable from the reactor without the necessity of draining the reactor vessel. This feature has proven to be worthwhile in operation. The mechanism is adaptable to reactors operating at pressures up to 1500 psi and requiring up to a 6-foot control rod stroke. This paper describes the development of the mechanism, the final design and proof-testing program, and some of the particular design difficulties encountered. Some of the other drive types, including electromagnetic jack, hydraulic, and rotary seal rack-and-pinion, considered for EBWR application, are also discussed.