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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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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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.
Isao Murata, Takamasa Mori, Masayuki Nakagawa
Nuclear Science and Engineering | Volume 123 | Number 1 | May 1996 | Pages 96-109
Technical Paper | doi.org/10.13182/NSE96-A24215
Articles are hosted by Taylor and Francis Online.
The method to treat randomly distributed spherical fuels in continuous energy Monte Carlo calculations has been established. In this method, the location of a spherical fuel is sampled probabilistically along the particle flight path from the spatial probability distribution of spherical fuels, called the nearest neighbor distribution. The necessary probability distribution was evaluated by a newly developed Monte Carlo hard sphere packing simulation code, which employs a random vector synthesis method to reduce overlaps of spherical fuels. The obtained probability distribution was validated by comparing a cross-section photograph of a real fuel compact and an X-ray diffraction experimental result. This method was installed in a Monte Carlo particle transport code and validated by an inventory check of spherical fuels and criticality calculations of ordered packing models. Also, an analysis of a critical assembly experiment was performed with the new code. As a result, it was confirmed that the method was applicable to practical reactor analysis. The method established is quite unique in the respect of probabilistically modeling the geometry of a great number of spherical fuels distributed randomly without any loss of the advantage of the continuous energy method.