This paper presents solutions for critical problems in Japan’s DEMO (JA DEMO), which include common DEMO design issues beyond ITER-relevant technologies. The highlights of this design study are (i) system design for electric power generation, (ii) remote maintenance concept to attain a high plant availability, and (iii) novel concept for water-cooled pebble bed blanket and tritium recovery....
The challenge
A power plant based on a tokamak architecture has a magnetic cage with thick shielding, so maintenance needs to be conducted through long narrow access ports (see figure 1). This means unprecedented dexterous handling of massive flexible components, which is difficult, slow and expensive. For this reason, industrial plant to date has always been arranged to allow the heaviest...
According to the European strategy to fusion energy, the development and the operation of a demonstration power plant (DEMO) is foreseen as the single step between ITER and a commercial tokamak fusion power plant (FPP). DEMO is required to feature all key systems and components of an FPP and to comply with a set of general goals [Donné, 2018]. These goals include a few hundred megawatts...
As the EUROfusion EU-DEMO design programme approaches the transition between the pre-conceptual and conceptual design phase the systems code PROCESS has been improved to incorporate more detailed plasma physics, engineering and integration models. Unlike many systems codes PROCESS combines the physics modelling with both technology and costs analysis. Key to the conceptual design phase are...
The 2018 National Academies of Sciences (NAS) Report of the Committee on a Strategic Plan for U.S. Burning Plasma Research and the more recent APS-DPP Community Planning Process (CPP) recommend that the U.S. should pursue innovative science and technology to enable construction of a Fusion Pilot Plant (FPP) that produces net electricity from fusion at reduced capital cost. Such a mission...
![RBt-space.][1]
![Q-dependence.][2]
![kappa-beta-space.][3]
Spherical Tokamak reactor (STR) is attractive due to its inherent capabilities such as disruption avoidance, natural elongation, natural divertor and high beta capability, apart from a smaller size, with presumably lower costs [ 1, 2]. There has been an extraordinary evolution from the early concepts like SMARTOR [ 3] with...
The use of high temperature superconductors (HTS) in magnetic systems of fusion devices enables magnetic fields over 16 T, unachievable with low temperature superconductors (LTS), and promises significant reduction in cryogenic and energy budget [1-4]. HTS materials are considered by some researcher groups as the enabling material to make magnetic confinement systems more compact and more...