An aqueous lithium salt blanket is designed as a candidate for the tritium production blanket of ITER. There are two rows of flat tube aqueous salt flow channels placed between beryllium blocks. The inboard and outboard blanket configurations have been optimized to maximize tritium breeding. A local outboard TBR of 1.44 is obtained using LiOH at a concentration of 5 g/100 cm3. The overall TBR d...

A minor actinides (MAs)-burning core system is proposed for future LMFBRs. It provides high-bumup, a long cycle length and enhanced safety characteristics. MAs are transmuted in two steps. MAs are mixed into the blanket fuel only. Pu, reprocessed from discharged blanket fuel, is mixed into the core fuel of an axially heterogeneous core (AHC). Advantages of this MAbuming system include reduction...

The paper reports results of MCNP-5 calculations to assess the effect on the Tritium Breeding Ratio (TBR) when integrating a distributed Ion Cyclotron Range of Frequencies (ICRF) antenna in the blanket of DEMO fusion power reactor. The calculations consider different parameters such as the ICRF covering ratio and the type of breeding blanket including the Helium Cooled Pebble Bed (HCPB) and the...

This paper proposes two local multifractal measures motivated by blanket method for calculation of fractal dimension. They cover both fractal approaches familiar in image processing. The first two measures (proposed Methods 1 and 3) support model of image with embedded dimension three, while the other supports model of image embedded in space of dimension three (proposed Method 2). While the cl...

A modular DCLL blanket is selected as the reference concept in the ARIES-CS power plant study. This concept is characterized by the following features: 1. Eutectic lead lithium alloy Pb-17Li serving as breeder and coolant (“self-cooled breeding zone”); 2. Helium-cooled FW and blanket structure made of the MF82H Reduced Activation Ferritic Steel (RAFS); 3. Flow channel inserts (FCI) made of SiCc...

Materials R & D in Japan is based on the national fusion R & D strategy, where fusion research is clearly defined as the energy oriented and time-driven to meet ITER and DEMO schedule with the early realization of electricity supply from fusion reactor system [1,2]. After more than two decades of the intensive research activities on fusion engineering at Universities and JAERI, these activities...

This paper presents a thermal-hydraulic analysis of a helium-cooled ceramic breeder blanket for the ITER. It is found that the blanket can operate at moderate pressure and temperatures, which coupled to the use of an inert gas, makes it particularly attractive from a safety standpoint. Transient analysis of the manifolding flow distribution indicates that the introduction of a diffusive plate a...

The key issues associated with the three maintenance approaches envisaged for the Compact Stellarator (CS) power core have been identified and addressed, and the layout of coil system, coil supporting structure, cryostats, vacuum vessel and maintenance ports have been conceptually defined. These are summarized in this paper. Blanket concepts compatible with the three maintenance approaches have...