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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.
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NRC seeks comments on new fee schedule for FY 2024
The Nuclear Regulatory Commission is asking for feedback on proposed changes to the annual, licensing, inspection, and special projects fees for fiscal year 2024.
The proposed fee rule, published February 20 in the Federal Register, is based on the FY 2024 Congressional Budget Justification as a full-year appropriation, but it has not yet been enacted. The final rule will be based on the NRC’s actual appropriation, and the agency will update the final fee schedule as appropriate.
K. Lisa Reed, Farzad Rahnema
Nuclear Technology | Volume 208 | Number 3 | March 2022 | Pages 562-574
Technical Note | doi.org/10.1080/00295450.2021.1935166
Articles are hosted by Taylor and Francis Online.
Previous work presented a set of stylized three-dimensional benchmark problems based on the Oak Ridge National Laboratory (ORNL) preconceptual design of a fluoride-salt-cooled small modular advanced high-temperature reactor, or SmAHTR, with prismatic assemblies fueled by tri-isotropic (TRISO) particles. That previous work created a detailed description of the benchmark problems by closing several outstanding design gaps from the ORNL preconceptual design report, notably by addressing the lack of active control mechanisms, for which control rod “bundles” were implemented.
In this technical note, the creation of two additional stylized benchmark problem sets based on that past work is detailed, offering two new control rod configurations. The fluoride salt, small size, and highly heterogeneous TRISO-fueled pins make these additional benchmark problem sets useful numerical validation references in benchmarking neutronics tools against continuous-energy stochastic Monte Carlo results. Detailed reference results, including the eigenvalue (keff) and 1/11th assembly-averaged relative fission density distributions, are provided for both control rod configurations in full-core cases with all control rods withdrawn and all control rods fully inserted. A near-critical core benchmark problem and results are provided for one configuration. The provided results are calculated using the continuous-energy Monte Carlo code MCNP.