The paper describes a series of large scale slab tests, as well as complementary component tests, which were carried out to develop the proposed shearhead system.
This paper reports on the prototype manufacturing, thermo-hydraulic modeling experiments and component tests, as well as on mechanical testing.
The objective of the project was to install an expected combined capacity of 5 MWth, supply it to the national grid and also to act as a facility for component testing [4].
In the first stage, K-DEMO will demonstrate a net electricity generation but will also act as a component test facility.
This device shall be tritium self-sufficient, produce net electricity, and acts as a component test facility to demonstrate fusion power plant relevant technologies, e.g. those of the breeding blanket.
K-DEMO is designed not only to demonstrate a net electricity generation and a self-sustained tritium cycle, but also to be used, in its initial stage, as a component test facility.
At first, a steady-state Korean DEMO Reactor (K-DEMO) is designed not only to demonstrate a net electricity generation and a self-sustained tritium cycle, but also to be used as a component test facility.
There has long been a view that it could have a key role as a component test facility, to complement ITER, IFMIF, and DEMO, and there are also interesting possibilities as an option for the fusion power source of an electricity plant.
The other system is a flexible test section for molten salt process technology and component tests, such as valves, solar receiver tubes and instrumentation.
A comprehensive code was established, which covered all current methods of verification, as e.g. component testing, nominal stress, structural stress, notch stress method as well as fracture mechanics assessment procedures.
The question then arises as to how component test plans should be designed so as to minimize test costs.
