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General Information

6th IAEA DEMO Programme Workshop (DPWS-6)

Moscow, Russian Federation
1–4 October 2019


The International Atomic Energy Agency (IAEA) will hold the Sixth IAEA DEMO Programme Workshop (DPWS-6) from 1 to 4 October 2019 in Moscow, Russian Federation. Previous workshops in the series were held in Los Angeles (2012), Vienna (2013), Hefei (2015), Karlsruhe (2016) and Daejeon (2018).

With the construction of the International Thermonuclear Experimental Reactor (ITER), the worldwide magnetic fusion programme has begun a transition from a fusion science activity to one aimed at producing fusion energy on an industrial, power plant scale. This is driving an increased emphasis on a fusion technology programme which, along with ITER and accompanying research, will bring fusion as a power source within our reach. While internationally there is no agreement on a single roadmap to fusion, the science and technology issues to be resolved for fusion power to become a reality are broadly agreed. Resolving these issues and understanding the options for next-step fusion nuclear facilities are of common interest, even if the emphases and priorities vary from nation to nation. Thus there is substantial scope to add value to the programme by international cooperation. Against this backdrop, the IAEA has established a series of annual Demonstration Fusion Power Plant (DEMO) Programme Workshops to facilitate international collaboration on defining and coordinating DEMO programme activities


The main purpose of this sixth workshop in the series is to discuss a subset of key DEMO scientific and technical issues with the aim of defining the facilities and programme activities that can lead to their resolution. The workshop output, to be documented in summary presentations and a report to the IAEA and subsequent journal publication, will be information that could be used by any party as input for the planning of activities on the path to a DEMO facility. Opportunities to make greater progress through international collaboration will be identified, ideally leading to coordination or joint work where beneficial. To promote continuity in the workshop series, participants will propose the set of topics for the next workshop(s) in the series, considering the status, expected progress and need for international discussion with regard to the various DEMO issues.


17 June 2019

Deadline for submission of abstracts for poster contributions (

21 June 2019

Deadline for submission of Forms A, B and C through the appropriate governmental authority

28 June 2019

Participants will be informed about the acceptance of their pape

28 June 2019

Grant will be awarded

1 October 2019

Event begins



1. Plasma transients, disruptions & ELMs including effects in stellarators

While conceptual design studies of DEMO and Fusion Power Plants often assess stationary conditions, transients are ubiquitous in magnetically confined plasmas and their effect should be considered in the design of tokamak and stellarator DEMO devices from the beginning. The transients that may have strong implications for the design and hence need to be controlled or avoided will be analysed. Where this is not possible in a reliable manner their consequences need to be mitigated. In particular, the following items will be addressed:
• Sudden loss of stored energy (thermal quench, radiative collapse) in tokamaks and stellarators
• Sudden loss of plasma current (disruption) in tokamaks
• Sudden loss of edge transport barrier (ELMs, filamentary bursts) in tokamaks and stellarators
• Transients produced by a loss of control (e.g. divertor re-attachment)
• ‘Foreseeable’ transient phases such as the ramp-up or ramp-down phases

The Topic will cover the present physics understanding of the occurrence of these events, the expected loading conditions arising from the transients and methods for transient avoidance or control or mitigation of their consequences.

2. Irradiation damage and lifetimes of materials, components. Impact of operational conditions.

Damage caused by neutron irradiation, such as displacement damage and gaseous and solid transmutation products, is a key lifetime limiting issue for in-vessel components of any material used in a fusion reactor. This includes structural, armour, and blanket functional materials. Neutron damage implies degradation of properties and activation of materials, and therefore impacts performance and safety aspects. There is a highly non-linear, multidimensional and complex interplay among the different damage types, the operational conditions (e.g., operation temperature, thermal and mechanical loading conditions) and likely achievable lifetime and performance. As the fusion neutron spectrum is distinctively different from that in available fission reactors, and a fusion neutron source is not yet at hand, best estimates on neutron irradiation impact based on various experiments and modelling are indispensable for the conceptual design phase of a fusion reactor, while for the engineering design phase validated data will be required to inform safety reports and licensing.

The aim of the Topic is to provide an overview of present knowledge from irradiation experiments, post-irradiation examinations and modelling approaches. The Topic will consider the irradiation damage to be expected in fusion reactors for the critical elements of the in-vessel components and on the lifetime predictions to be derived for the different concepts for breeding blanket and divertor, taking into account the respective materials and operation conditions. Furthermore, the data gaps which still exist, and the approaches and the time scales to close them, will be identified, as well as approaches to develop engineering design methodologies and criteria for in-vessel components.

3. Materials engineering of PFCs & PFMs

The Topic will address the major material challenges for the divertor and first wall of DEMO-class machines. For tungsten PFCs, major issues include:
• Strengthening and toughening to decrease the DBTT and to increase the recrystallization temperature
• Thermal fatigue failure and surface damage by transient heat load
• Mechanical / physical properties degradation by neutron irradiation and nuclear transmutation including heat sink materials
• Tritium retention
• Oxidation in case of an accidental exposure to air or coolant
• Metals bonding and joining reliabilities

The Topic will assess the extent to which these issues can be resolved by developing advanced W alloys and composites, utilizing advanced manufacturing technologies and liquid metal concepts. The Topic will discuss the requirements for future material engineering research towards the construction of DEMO including material databases, scale-up of material products from laboratory to industrial levels, supply chains, component manufacturing and testing of PFCs and PFMs under the DEMO-relevant conditions.

And the following Special Topics:
• Russian Federation Fusion Programme
• The new US Fusion Technology Programme
• New multi-scale modelling approaches for predicting engineering quantities in irradiated materials
• Construction of a dedicated Fusion Neutron Machine: DONES

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