Impact of the SiC FCI in the DCLL blanket module on the nuclear environment inside a Demo reactor configuration

Author

Youssef, Mahmoud Z. ; Morley, Neil B. ; Dagher, Mohamed

Author_Institution

Mech. & Aerosp. Eng. Dept., Univ. of California - Los Angeles, Los Angeles, CA, USA

fYear

2009

fDate

1-5 June 2009

Firstpage

1

Lastpage

6

Abstract

The effects of the inclusion of the SiC flow channel insert (FCI) in a dual-coolant lithium-lead (DCLL) blanket placed in a representative Demo reactor on various key neutronics parameters are studied. These parameters are: tritium production ratio (TBR), power multiplication (PM), profiles of nuclear heating, peak damage parameters (dpa, helium and hydrogen production rates) in the structure, vacuum vessel and shield, peak heating rate and fast neutron fluence in the TF coils. Various thicknesses and density factors of the FCI are considered. These effects are examined in both radial and toroidal direction by 1-D and 2-D models.

Keywords

fusion reactor blankets; fusion reactor theory; tritium handling; DCLL blanket module; Demo reactor configuration; SiC flow channel insert; TF coils; density factors; dual-coolant lithium-lead blanket; fast neutron fluence; neutronics parameters; nuclear environment; nuclear heating profiles; peak damage parameters; power multiplication; shield; toroidal direction; tritium production ratio; vacuum vessel; Aerospace engineering; Dielectrics and electrical insulation; Heating; Helium; Inductors; Neutrons; Plasma temperature; Production; Silicon carbide; Steel; DCLL Blanket; Neutron Trasport; Neutronics; Power Multiplication; Radiation Damage; SiC Flowing Channel Insert; Tritium Breeding Ratio;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 2009. SOFE 2009. 23rd IEEE/NPSS Symposium on

Conference_Location

San Diego, CA

Print_ISBN

978-1-4244-2635-5

Electronic_ISBN

978-1-4244-2636-2

Type

conf

DOI

10.1109/FUSION.2009.5226368

Filename

5226368