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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
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.
Y. Y. Chang, S. K. Loyalka
Nuclear Science and Engineering | Volume 77 | Number 2 | February 1981 | Pages 235-250
Technical Note | doi.org/10.13182/NSE81-A21357
Articles are hosted by Taylor and Francis Online.
A computer code TWOLASER has been developed for neutronic calculations of square lattice cells in nuclear power reactors. The computer code, which uses new methods for solutions of the integral transport equation and burnup equations, has been used to assess the accuracy and speed of the LASER code. The new code considers actual two-dimensional geometry of the cell as compared to the one-dimensional approximation used by LASER. Calculations have been performed on a sample problem for a burnup of 10.6 MWd/kg fissile. Results from these calculations show that the one-dimensional approximation used by LASER is good for the sample problem. However, the method used by LASER for the solution of burnup equations is not efficient. A modified version, MLASER, of the LASER code has also been developed in this research. This version uses the one-dimensional approximation of LASER and the new method for the solution of burnup equations, and it also provides good results as compared to the results given by the two-dimensional code. However, for the same accuracy, MLASER is computationally much faster (a factor of 4) than the original LASER program. The code TWOLASER can be used to provide data for benchmarking, and MLASER can be used for the replacement of the original LASER.