[HTML][HTML] APOLLO3 homogenization techniques for transport core calculations—application to the ASTRID CFV core
JF Vidal, P Archier, B Faure, V Jouault, JM Palau… - Nuclear Engineering …, 2017 - Elsevier
JF Vidal, P Archier, B Faure, V Jouault, JM Palau, V Pascal, G Rimpault, F Auffret…
Nuclear Engineering and Technology, 2017•ElsevierThis paper presents a comparison of homogenization techniques implemented in the
APOLLO3 platform for transport core calculations: standard scalar flux weighting and new
flux–moment homogenization, in different combinations with (or without) leakage models.
Besides the historical B1-homogeneous model, a new B-heterogeneous one has indeed
been implemented recently in the two/three-dimensional-transport solver using the method
of characteristics. First analyses have been performed on a very simple Sodium Fast …
APOLLO3 platform for transport core calculations: standard scalar flux weighting and new
flux–moment homogenization, in different combinations with (or without) leakage models.
Besides the historical B1-homogeneous model, a new B-heterogeneous one has indeed
been implemented recently in the two/three-dimensional-transport solver using the method
of characteristics. First analyses have been performed on a very simple Sodium Fast …
Abstract
This paper presents a comparison of homogenization techniques implemented in the APOLLO3 platform for transport core calculations: standard scalar flux weighting and new flux–moment homogenization, in different combinations with (or without) leakage models. Besides the historical B1-homogeneous model, a new B-heterogeneous one has indeed been implemented recently in the two/three-dimensional-transport solver using the method of characteristics. First analyses have been performed on a very simple Sodium Fast Reactor core with a regular hexagonal lattice. They show that using the heterogeneous leakage model in association with flux-moment homogenization strongly improves the prediction of keff and void reactivity effects. These good results are confirmed when the application is done to the fissile assemblies of the more complex CFV (Low Void Effect) core of the ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) project of sodium-cooled fast breeder reactor (Generation IV).
Elsevier
以上显示的是最相近的搜索结果。 查看全部搜索结果