Neutronic analysis of sodium‐cooled fast reactor design with different fuel types using modified CANDLE shuffling strategy in a radial direction
Author:
Affiliation:
1. Department of Physics Andalas University Padang Indonesia
2. Department of Physics Jember University Jember Indonesia
3. Nuclear and Biophysics Laboratory Bandung Institute of Technology Bandung Indonesia
Publisher
Wiley
Subject
Energy Engineering and Power Technology,Fuel Technology,Nuclear Energy and Engineering,Renewable Energy, Sustainability and the Environment
Link
https://onlinelibrary.wiley.com/doi/pdf/10.1002/er.6384
Reference34 articles.
1. The multiscale thermal‐hydraulic simulation for nuclear reactors: A classification of the coupling approaches and a review of the coupled codes
2. Agency OECD Nuclear Energy SC for N.Benchmark for neutronic analysis of sodium‐cooled fast reactor cores with various fuel types and core sizes. Nuclear Energy Agency; February2016:87.
3. The Status of Generation IV Sodium-Cooled Fast Reactor Technology Development and its Future Project
4. THE INVESTIGATION OF BURNUP CHARACTERISTICS USING THE SERPENT MONTE CARLO CODE FOR A SODIUM COOLED FAST REACTOR
5. An Advanced Sodium-Cooled Fast Reactor Core Concept Using Uranium-Free Metallic Fuels for Maximizing TRU Burning Rate
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