Neutronic and thermal calculation of blanket for high power operating condition of fusion reactor

Conference · Sat Dec 31 04:00:00 EST 1994

OSTI ID:197002

Sagawa, H; Shimakawa, S; Kuroda, T ^[1]

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1. Oarai Research Establishement of JAERI, Ibaraki (Japan); and others

Internal (breeding region) structures of ceramic breeder blanket to accommodate high power operating conditions such as a DEMO reactor have been investigated. The conditions considered here are the maximum neutron wall load of 2.8 MW/m{sup 2} at outboard midplane corresponding to a fusion power of 3.0 GW and the coolant temperature of 200{degrees}C. Structure of a blanket is based on the layered pebble bed concept, which has been proposed by Japan since the ITER CDA. Lithium oxide with 50% enriched {sup 6}Li is used in a shape of small spherical pebbles which are filled in a 316SS can avoid its compatibility issue with Be. Beryllium around the breeder can is filled also in a shape of spherical pebbles which works not only as a neutron multiplier but also as a thermal resistant layer to maintain breeder temperature for effective in-situ tritium recovery. Diameters and packing fractions of both pebbles are {<=} 1 mm and 65%, respectively. A layer of block Be between cooling panels is introduced as a neutron multiplier (not as the thermal resistant layer) to enhance tritium breeding performance. Inlet temperature of water coolant is 200{degrees}C to meet the high temperature conditioning requirement to the first wall which is one of walls of the blanket vessel. Neutronics calculations have been carried out by one-dimensional transport code, and thermal calculations have also been carried out by one-dimensional slab code.

• OSTI ID: 197002
• Report Number(s): CONF-940664--
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BREEDING BLANKETS
BREEDING PELLETS
LITHIUM 6
LITHIUM OXIDES
NEUTRON REFLECTORS
STAINLESS STEEL-316
THERMAL ANALYSIS
WALL LOADING
WATER