-
UKAEA-STEP-PR(24)122024
Ensuring tritium fuel self-sufficiency while maintaining continuous and high specification fuel flow to the tokamak via a low tritium inventory and controllable fuel cycle is a significant challenge to the STEP plant design. Effective and high-quality fuelling and exhausting is required to sustain and control a stable plasma, whereas fuel suffic…
-
UKAEA-STEP-CP(24)052023
The STEP (Spherical Tokamak for Energy Production) Programme aims to deliver a UK prototype fusion energy plant, targeting 2040, and a path to commercial viability of fusion. To deliver on this aim, we have performed initial scoping to identify the design point for a spherical tokamak prototype powerplant producing at least 100 MWe of…
-
UKAEA-CCFE-PR(23)1752022
In-vessel plasma facing components in fusion reactors such as ITER and DEMO experience high thermal loads and require active cooling, for which water is one possible coolant. The solution where plasma facing components utilise tungsten blocks as sacrificial armour has a joint internal structure of cooling tubes made from the copper base (~99% Cu…
-
UKAEA-CCFE-CP(20)1172020
The next generations of nuclear fusion reactors, including ITER and DEMO, will consider several different cooling systems for heat dissipation, power generation and tritium breeding. This includes the water-cooled lithium-lead blanket (WCLL) design, which bears significant similarities to the water-cooled circuit in a pressurised water fission reac…
-
UKAEA-CCFE-CP(20)802018
The European DEMO design will potentially use single phase water cooling in various components that require protection against corrosion damage. Coolant conditions will be similar to fission PWRs but with additional considerations arising from the materials of choice (Eurofer, CuCrZr), 14 MeV neutron irradiation, the presence of tritium, and strong…
-
UKAEA-CCFE-CP(20)792018
The Chinese Fusion Engineering Test Reactor (CFETR) bridges the gap between ITER and a demonstration fusion power plant (DEMO). The primary objectives of CFETR are: demonstrate tritium self-sufficiency, ~1GW fusion power, operate in steady-state and have a duty cycle of 0.3-0.5 [1]. CFETR is in the pre-conceptual design phase and is currently envis…
-
CCFE-PR(16)052016
PROCESS is a reactor systems code it assesses the engineering and economic viability of a hypothetical fusion power station using simple models of all parts of a reactor system. PROCESS allows the user to choose which constraints to impose and which to ignore, so when evaluating the results it is vital to study the list of constraints used. New …
-
CCFE-PR(17)342015
The current baseline concept for a European DEMO defines a pulsed reactor producing power for periods of 24 h at a time, interrupted by dwell periods of approximately half an hour, potentially leading to cyclic fatigue of the heat transfer system and power generation equipment. Thermal energy storage systems could mitigate pulsing issues; however…
-
2013
If fusion power reactors are to be feasible, it will still be necessary to convert the energy of the nuclear reaction into usable form. The heat produced will be removed from the reactor core by a primary coolant, which might be water, helium, molten lithium-lead, molten lithium-containing salt, or CO 2 . The heat could then be transferred to a con…
Showing 1 - 9 of 9 UKAEA Paper Results
Page 1 of 1