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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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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.
Kohtaro Ueki, Yoshihito Namito
Nuclear Science and Engineering | Volume 96 | Number 1 | May 1987 | Pages 30-38
Technical Paper | doi.org/10.13182/NSE87-A16361
Articles are hosted by Taylor and Francis Online.
Integral shielding experiments using iron-polyethylene slab shields were carried out to determine an optimum arrangement for the neutron dose rate. The total thickness of the iron slabs was fixed at 32 cm, while several thicknesses of polyethylene slabs were employed as a parameter. Some measured data were analyzed by the Monte Carlo code MORSE-CG with the splitting technique. Depending on the location of the polyethylene slab, the measured neutron dose rates changed remarkably in the iron-polyethylene shielding system. When the polyethylene slab was 1 cm thick, the ratio of the maximum neutron dose rate to the minimum value was 1.3, and the ratio was increased to as much as 5.4 for the 14-cm-thick polyethylene slab. The minimum dose point (i.e., optimum shielding arrangement) was observed when the polyethylene slab was located near the detector with the iron slab placed near the neutron source. This was also demonstrated by the Monte Carlo calculations.