Results 21 to 30 of about 647 (119)
Generation and application of interface discontinuity factors in the reactor simulator DYN3D [PDF]
, 2014 Däubler, M., Jimenez, J., Sanchez, V.
core +5 more sources
Burnup Credit Evaluation for BWR Spent Fuel from Full Core Calculations
Applied Sciences, 2020 Due to the challenges of spent fuel accumulation, the nuclear industry is exploring more cost-effective solutions for spent fuel management. The burnup-credit method, in application for storage and transport of the spent fuel, gained traction over recent
Anna Detkina +3 more
doaj +1 more source
Specifications for a coupled neutronics thermal-hydraulics SFR test case [PDF]
, 2017 Coupling neutronics/thermal-hydraulics calculations for the design of nuclear reactors is a growing trend in the scientific community. This approach allows to properly represent the mutual feedbacks between the neutronic distribution and the thermal ...
TASSONE, ALESSANDRO
core +1 more source
Extension of the analytic nodal diffusion solver ANDES to triangular-Z geometry and coupling with COBRA-IIIc for hexagonal core analysis. [PDF]
, 2010 In this paper the extension of the multigroup nodal diffusion code ANDES, based on the Analytic Coarse Mesh Finite Difference (ACMFD) method, from Cartesian to hexagonal geometry is presented, as well as its coupling with the thermal–hydraulic (TH) code ...
Aragonés +16 more
core +2 more sources
Science and Technology of Nuclear Installations, Volume 2018, Issue 1, 2018., 2018 The molten salt reactor (MSR) is one of the six advanced reactor concepts selected by Generation IV International Forum (GIF) because of its inherent safety and the promising capabilities of TRU transmutation and Th‐U breeding. In this study, a three‐dimensional thermal‐hydraulic model (3DTH) is developed for evaluating the steady‐state performance of ...
Long He +6 more
wiley +1 more source
CTF/DYN3D multi-scale coupled simulation of a rod ejection transient on the NURESIM platform
Nuclear Engineering and Technology, 2017 In the framework of the EU funded project NURESAFE, the subchannel code CTF and the neutronics code DYN3D were integrated and coupled on the NURESIM platform.
Yann Périn, Kiril Velkov
doaj +1 more source
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
Understanding and ameliorating non-linear phase and amplitude responses in AMCW Lidar [PDF]
, 2011 Amplitude modulated continuous wave (AMCW) lidar systems commonly suffer from non-linear phase and amplitude responses due to a number of known factors such as aliasing and multipath inteference. In order to produce useful range and intensity information
Cree, Michael J. +2 more
core +3 more sources
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