Published October 2017 | Version v1
Journal article

APOLLO3 homogenization techniques for transport core calculations- application to the ASTRID CFV core

Description

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)

Additional details

Publishing Information

Journal Title
Nuclear Engineering and Technology
Journal Volume
49
Journal Issue
7
Series
17 refs, 9 figs, 3 tabs
Journal Page Range
p. 1379-1387
ISSN
1738-5733

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
49063887
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
COMPUTER CALCULATIONS; FORECASTING; LEAKS; REACTOR CORES; SODIUM COOLED REACTORS; TRANSPORT; USES; VOIDS
Descriptors DEC
LIQUID METAL COOLED REACTORS; REACTOR COMPONENTS; REACTORS