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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 Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Latest News
NRC updating GEIS rule for new nuclear technology
The Nuclear Regulatory Agency is issuing a proposed generic environmental impact statement (GEIS) for use in reviewing applications for new nuclear reactors.
In an April 17 memo, NRC secretary Carrie Safford wrote that the commission approved NRC staff’s recommendation to publish in the Federal Register a proposed rule amending 10 CFR Part 51, “Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions.”
Seul-Been Kim, Jaeho Lee, Goon-Cherl Park, Hyoung Kyu Cho (Seoul National Univ)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 772-776
The necessity of the latest codes and methods for safety demonstration is increased to satisfy new safety requirement and achieve improved margin management. In this circumstance, it becomes an important issue that high-fidelity and multi-physics simulation with coupled T/H (Thermal-Hydraulics) and neutronics code for light water reactor whole core. With the improved computing power, the subchannel scale T/H analysis could be used as a suitable tool for pin-by-pin whole core simulation considering both accuracy of simulation and reasonable calculation time.
CUPID is a multi-dimensional two-phase flow analysis code developed by KAERI for the analysis of reactor core component. It has been validated against various experimental data and applied for practical nuclear applications. Recently, its applicability was extended to the subchannel scale T/H analysis. It is highly parallelized with the domain decomposition and message passing interface and these features facilitated the extension to use the code for the whole reactor core pipby- pin analysis in the subchannel scale. Required physical models for the subchannel scale analysis, for example, turbulent mixing and void drift models, were implemented and validated against available subchannel experiments.
In the present study, the grid spacer model was implemented for the enhancement of accuracy of the simulation. Afterwards, the mixing vane model was implemented considering lateral momentum exchange between adjacent subchannels by the mixing vane. For the validation of models, PSBT 5x5 experiment was simulated using CUPID, and the calculation result was compared with the CTF calculation. These implemented models can contribute to improve the prediction capability of CUPID for more realistic whole reactor core transient analysis.