A breeding blanket design for the tritium production ICF reactor SIRIUS-T is presented. The blanket consists of alternating layers of beryllium multiplier and lithium breeder/coolant with vanadium alloy structure. A tritium breeding ratio of 1.9 can be achieved for the optimum layered configuration with lithium enriched to 90% 6Li. An optimum coolant routing scheme is utilized to achieve adequa...

Ideally, the ITER base blanket would provide the necessary tritium for the reactor to be self-sufficient during operation, while having minimal impact on the overall reactor cost, reliability and safety. A solid breeder blanket has been developed in the CDA phase in an attempt to achieve such objectives. The reference solid breeder base blanket configurations at the end of the CDA phase has man...

There is no practical external source of tritium for fusion energy development beyond ITER and all subsequent fusion systems have to breed their own tritium. To ensure tritium self-sufficiency, the calculated achievable tritium breeding ratio (TBR) should be equal to or greater than the required TBR. The potential of achieving tritium self-sufficiency depends on many system physics and technolo...

Dense self-supported Pd-alloy membranes are used to selectively separate hydrogen and hydrogen isotopes. In particular, deuterium (D) and tritium (T) are currently identified as the main elements for the sustainability of the nuclear fusion reaction aimed at carbon free power generation. In the fusion nuclear reactors, a breeding blanket produces the tritium that is extracted and purified befor...

1 1. In troduc tion 1 2. Breeding Blanket Design and Materials 2 3. Tritium Breeding Requirements 8 4. Breeding Potential of Candidate Materials 14 4.1 Effects of Penetrations on T 15 4.2 Breeding in the Inboard Blanket 18 4.3 Fast and Thermal Systems 19 4.4 Neutron Multipliers 24 4.5 Conclusions on Breeding Potential 30 5. Sensitivity to Data Uncertainties 32 6. Recommended Effort 40 7. Nuclea...

An In-depth analysis of the INT05 tritium-production—blanket design Is presented. A ternary system of solid silicate breeder, lead neutron multiplier, and graphite moderator is explored primarily from safety and blanket tritium-inventory considerations. Lithiumsilicate (Li2Si03) bleeder systems are studied along 2 with water (H2P/D2O) and Type 316 stainless steel as coolant and structural mater...

Numerical simulation of tritium permeation from breeding zones to the coolant in the helium cooled pebble-bed blanket is performed in this paper. 2D and 3D convection–diffusion models are developed to account for the effects of purge stream convection. Incompressible transient Brinkman model with variable permeability is used in flow calculation, and transient diffusion and convection equations...

A concise overview is given on materials applied in fusion technology. The influence of plasma operation on the behaviour of reactor components and diagnostic systems is discussed with emphasis on effects caused by fast particles reaching the reactor wall. Issues related to primary and induced radioactivity are reviewed: tritium inventory and transmutation. Tritium breeding in the reactor blank...

For the first time, nuclear properties are experimentally examined on the water cooled pebble bed blanket by using DT neutrons with two partial mockups; multi-layered mockup with water and pebble bed mockup. Prediction uncertainties are clarified on tritium production rate (TPR) through the experimental analyses. From the multi-layered mockup experiment, it is found that integrated tritium prod...