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Division Spotlight
Nuclear Nonproliferation Policy
The mission of the Nuclear Nonproliferation Policy Division (NNPD) is to promote the peaceful use of nuclear technology while simultaneously preventing the diversion and misuse of nuclear material and technology through appropriate safeguards and security, and promotion of nuclear nonproliferation policies. To achieve this mission, the objectives of the NNPD are to: Promote policy that discourages the proliferation of nuclear technology and material to inappropriate entities. Provide information to ANS members, the technical community at large, opinion leaders, and decision makers to improve their understanding of nuclear nonproliferation issues. Become a recognized technical resource on nuclear nonproliferation, safeguards, and security issues. Serve as the integration and coordination body for nuclear nonproliferation activities for the ANS. Work cooperatively with other ANS divisions to achieve these objective nonproliferation policies.
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.
Mildred J. Bradley, Leslie M. Ferris
Nuclear Science and Engineering | Volume 8 | Number 5 | November 1960 | Pages 432-436
Technical Paper | doi.org/10.13182/NSE60-A25825
Articles are hosted by Taylor and Francis Online.
A grind-leach method for the recovery of uranium from high-density graphite fuel elements containing greater than 5 weight per cent uranium has been developed on a laboratory scale as a head-end treatment for standard tributyl phosphate solvent extraction processes. With fuel ground to −16 mesh, greater than 99.8% of the uranium can be recovered by leaching twice with boiling 15.8 M nitric acid. Uranium recoveries were lower with less concentrated acid, and with fuel of larger particle size or lower uranium concentration. The grind-leach method is not applicable to fuels containing less than 3% uranium. Leaching −16+30 mesh samples of a fuel containing 1.5% uranium and 7.2% thorium with either boiling 15.8 M nitric acid or 15.8 M nitric acid−0.04 M sodium fluoride, resulted in uranium and thorium recoveries of 90 and 86%, respectively.