APOLLO3 homogenization techniques for transport core calculations- application to the ASTRID CFV core
Creators
- 1. CEA, Gif-sur-Yvette (France)
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