27th IEEE Symposium on Fusion Engineering

Session

T.OA2: Divertors and PFCs: Tungsten

T.OA2

6 Jun 2017, 10:40

Marriott Shanghai City Center

424. TUNGSTEN TECHNOLOGY DEVELOPMENT IN KOREA AND ITS APPLICATION TO KSTAR EXPERIMENTS

Dr Suk-Ho Hong (National Fusion Research Institute)

06/06/2017, 10:40

Plasma facing components

Invited Oral

Main focus of fusion engineering has been moved towards development of metal wall plasma facing components (PFCs) and corresponding interaction between plasma and metal wall. National Fusion Research Institute (NFRI) has started metal wall related research activities since 2012, which are closely related to major upgrade of KSTAR and research on K-DEMO. As the first step, metal bonding...

496. Investigation of ITER-grade tungsten under very high heat loads.

Mr Leonid Khimchenko (ITER RFDA)

06/06/2017, 11:00

Divertors and high heat flux components

Invited Oral

Experiments carried out on advanced large tokamaks showed effective use of tungsten for making in-Vessel Components, interacting with the plasma. However, in reactor size fusion devices such as ITER and DEMO, are expected the critical loads on the divertor plates both in quasistationary stage and in pulsed events (disruption, VDE, ELMs et al.), High heat loads can cause not only increased...

183. Tungsten monoblock concepts for the U.S. Fusion Nuclear Science Facility (FNSF) first wall and divertor

Mr Yue Huang (UCLA)

06/06/2017, 11:20

Divertors and high heat flux components

Oral

Next-step fusion nuclear devices require plasma-facing components that can survive a much higher neutron dose than ITER, and in many design concepts also require higher operating temperatures, higher reliability, and materials with more attractive safety and environmental characteristics. In search of first wall concepts that can withstand surface heat fluxes beyond 2 MW/m$^2$, we analyzed...

318. Thermal Stress Evaluation on the Optimized Shaping Design for Tungsten Monoblock in EAST Divertor

Mr Xiahua Chen (Institute of Plasma Physics Chinese Academy of Sciences, University of Science and Technology of China)

06/06/2017, 11:40

Divertors and high heat flux components

Oral

Abstract—This paper investigates the issue of leading edge for EAST tungsten divertor monoblock which is also concerned in ITER project. Besides the positive effects like reduced risk of cracking, the castellation will lead to the increased probability of melting of the castellated divertor due to local power load on leading edge of the gap. That may introduce unacceptable amount of...

512. Precipitation of transmutant elements in neutron irradiated tungsten

Dr Xunxiang Hu (Oak Ridge National Laboratory)

06/06/2017, 12:00

Plasma facing components

Oral

As the leading plasma facing material in fusion reactors, tungsten is confronted with extremely hostile environment, characterized by high temperature, and high fluxes of heat and particles (i.e., D, T, He, and neutrons). One of the primary concerns is the generation of transmutation elements (i.e., Re, Os) and the subsequent radiation-induced segregation and precipitation, and the resulting...

204. Defect production and deuterium bulk retention in quasi-homogeneously damaged tungsten

Dr Feng Liu (Institute of Plasma Physics, Chinese Academy of Sciences)

06/06/2017, 12:20

Tritium extraction and control

Oral

Tungsten (W) is foreseen as the leading plasma facing material (PFM) for future fusion reactors due to its advantageous thermal mechanical properties and relatively low solubility of tritium (T). W-PFM in fusion reactors will experience intense radiation by 14 MeV-peaked neutrons (n), which have long mean free paths on the order of centimeters in solids. T retention in W may greatly increase...