Results 21 to 30 of about 94 (78)
Fluids, 2020 The aim of the numerical study was the detection of possible vortices in the upper part of the core of a Pre-Konvoi Pressurized Water Reactor (PWR) which could lead to temperature cycling.
Thomas Höhne, Sören Kliem
doaj +1 more source
Science and Technology of Nuclear Installations, Volume 2013, Issue 1, 2013., 2013 The use of fine distributed moderating material to enhance the feedback effects and to reduce the sodium void effecting SFRs is described. The drawback on the feedback effects due to the introduction of minor actinides into SFR fuel is analyzed. The possibility of compensation of the effect of the minor actinides on the feedback effects by the use of ...
Bruno Merk, Wei Shen
wiley +1 more source
Science and Technology of Nuclear Installations, Volume 2013, Issue 1, 2013., 2013 The use of fine distributed moderating material to enhance the feedback effects and to reduce the sodium void effect in sodium‐cooled fast reactor cores is described. The influence of the moderating material on the fuel assembly geometry, the neutron spectrum, the feedback effects, the power and burnup distribution, and the transmutation performance is
Bruno Merk, Konstantin Mikityuk
wiley +1 more source
Development of Cross-Section Library for DYN3D Code
Nuclear and Radiation Safety, 2014 At present, SSTC NRS uses the HELIOS code for generation of few-group cross-section libraries for WWER core calculations. There is an urgent issue of selecting the appropriate approach to implement the cross-section library into the DYN3D code. The paper overviews the application of approaches used by SSTC NRS, such as a multidimensional table and ...
V. Khalimonchuk +3 more
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Determination of volume of radioactive waste in activated VVER-1200 reactor structures
Весці Нацыянальнай акадэміі навук Беларусі: Серыя фізіка-тэхнічных навукThe results of calculation studies of the amount of solid high-level, intermediate-level, low-level, very lowlevel radioactive waste (HLW, ILW, LLW, VLLW, respectively) generated during neutron activation of structural materials adjacent to the core of ...
M. L. Zhemzhurov +6 more
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Validation of Pin Power Calculations Using DYN3D on MIDICORE Benchmark
Nuclear and Radiation Safety, 2019 Three-dimensional code DYN3D is widely used for the calculation of steady states and transients in light water reactors with hexagonal fuel assemblies like VVER. The capability of pin-by-pin power calculation is implemented in the code through an intranodal power reconstruction approach.
M. Ieremenko +3 more
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The 3-Dimensional Core Model DYN3D
, 1999 Analyzing the safety margins in transients and accidents of nuclear reactors 3-dimensional models of the core were used to avoid conservative assumptions needed for point kinetics or 1-dimensional models. Therefore the 3D code DYN3D has been developed for the analysis of reactivity initiated accidents (RIA) in thermal nuclear reactors.
Grundmann, U., Mittag, S., Rohde, U.
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Extension of the nodal code DYN3D to SFR applications
, 2019 DYN3D is a well-established Light Water Reactor (LWR) simulation tool and is being extended for safety analyses of Sodium cooled Fast Reactors (SFRs) at the Helmholtz-Zentrum Dresden-Rossendorf. This thesis focuses on the first stage of the development process, that is, the extension and application of DYN3D for steady-state and transient SFR ...
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VVER-440 Full Core Benchmark Solutions with DYN3D
Conference paper presented at PHYSOR 2026 - The International Conference on Physics of Reactors. Published in Proceedings of PHYSOR 2026 International Conference. ISBN: 979-12-81583-46-7. Conference website: https://www.physor2026.org/. Session: R05. Verification and Validation of Methods and Codes. Paper ID: 62. Copyright transferred to Politecnico di
M. Zilly, E. Baran, Y. Bilodid, R. Henry
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Development of an advanced neutron transport solver for zooming in DYN3D
, 2017 Published by ...
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