Preliminary study on flexible core design of super FBR with multi-axial fuel shuffling
- 1. Waseda Univ., Graduate School of Advanced Science and Engineering, Tokyo (Japan)
Description
Preliminary study has been conducted on developing a new flexible core design concept for the Supercritical water-cooled Fast Breeder Reactor (Super FBR) with multi-axial fuel shuffling. The proposed new concept focuses on the characteristic large axial coolant density change in supercritical water cooled reactors (SCWRs) when the coolant inlet temperature is below the pseudocritical point and large coolant enthalpy rise is taken in the core for achieving high thermal efficiency. The aim of the concept is to attain both the high breeding performance and good thermal-hydraulic performance at the same time. That is, short Compound System Doubling Time (CSDT) for high breeding, large coolant enthalpy rise for high thermal efficiency, and large core power. The proposed core concept consists of horizontal layers of mixed oxide (MOX) fuels and depleted uranium (DU) blanket layers at different elevation levels. Furthermore, the upper core and the lower core are separated and independent fuel shuffling schemes in these two core regions are considered. The number of fuel batches and fuel shuffling scheme of the upper core were changed to investigate influence of multi-axial fuel shuffling on the core characteristics. The core characteristics are evaluated with-three-dimensional diffusion calculations, which are fully-coupled with thermal-hydraulics calculations based on single channel analysis model. The results indicate that the proposed multi-axial fuel shuffling scheme does have a large influence on CSDT. Further investigations are necessary to develop the core concept. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of 2017 international congress on advances in nuclear power plants (ICAPP2017)
- Imprint Pagination
- 2573 p.
- Journal Page Range
- 8 p.
Conference
- Title
- 2017 international congress on advances in nuclear power plants
- Acronym
- ICAPP2017
- Dates
- 24-25 Apr 2017; 26-28 Apr 2017
- Place
- Fukui (Japan); Kyoto (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 49024724
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- DEPLETED URANIUM; FBR TYPE REACTORS; FUEL ASSEMBLIES; FUEL MANAGEMENT; MIXED OXIDE FUELS; NEUTRON DIFFUSION EQUATION; REACTOR CORES; REACTOR DESIGN; REACTOR FUELING; SUPERCRITICAL STATE; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS; WATER COOLED REACTORS
- Descriptors DEC
- ACTINIDES; BREEDER REACTORS; DESIGN; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; ELEMENTS; ENERGY SOURCES; EPITHERMAL REACTORS; EQUATIONS; FAST REACTORS; FLUID MECHANICS; FUELS; HYDRAULICS; MANAGEMENT; MATERIALS; MECHANICS; METALS; NUCLEAR FUELS; NUCLEAR MATERIALS MANAGEMENT; PARTIAL DIFFERENTIAL EQUATIONS; REACTOR COMPONENTS; REACTOR LIFE CYCLE; REACTOR MATERIALS; REACTORS; SOLID FUELS; URANIUM
Optional Information
- Notes
- Available as CD-ROM Data in PDF format. Folder Name: pdf; Paper ID: 17194.pdf; 17 refs., 7 figs., 4 tabs.