Thermal–mechanical test on ITER primary first wall mock-ups

Dell’Orco, G.; Lorenzetto, P.; Malavasi, A.; Polazzi, G.; Simoncini, Michela; Venturi, Gianpietro; Zito, D.

doi:10.1016/s0920-3796(02)00156-4

Cited by 14 publications

(4 citation statements)

References 0 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The inlet cooling water temperature can be switched between 20 C and 140 C to magnify thermal stresses. 87) First test campaigns in EDA-BETA have shown, that this stress magnification can significantly reduce the life of first wall mock-ups, even for lower incident heat fluxes between 0.3 and 0.5 MW/m 2 . 88) In the last test campaign for EDA mock-ups with Gildcop Al25 have been successfully subjected to 8000 cycles of >0:6 MW/m 2 .…”

Section: Static Heat Loads By Infrared Heatermentioning

confidence: 99%

ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

2005

View full text Add to dashboard Cite

The current ITER design employs beryllium, carbon fiber reinforced composite and tungsten as plasma facing materials. Since these materials are exposed to high heat fluxes during the operation, it is essential to perform high heat flux tests for R&D of ITER components. Static heat loads corresponding to cycling loads during normal operation, are estimated to be up to 20 MW/m 2 in the divertor targets and around 0.5 MW/m 2 at the first wall in ITER. For the static high heat flux testing, tests in electron beam facilities, particle beam facilities, IR heater and in-pile tests have been performed. Another type, more critical heat loads, which have high power densities and short durations, corresponding to transient events, i.e. plasma disruption, vertical displacement events (VDEs) and edge localized modes (ELMs) deliver considerable heat flux onto the plasma facing materials. For this purpose, tests in electron beam (short pulses), plasma gun and high power laser facilities have been carried out. The present work summarizes the features of these facilities and recent experimental results as well as the current selection of ITER plasma facing components.

show abstract

Section: Static Heat Loads By Infrared Heatermentioning

confidence: 99%

ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

2005

View full text Add to dashboard Cite

show abstract

“…Many numerical simulations or experimental researches on different plasma-facing materials under ITER-relevant high heat flux or other various heat loads have been carried out. Dell'Orco et al [13] researched the thermal-mechanical calculations for Beryllium first wall (FW) mock-ups under a heat flux of 0.8 MW/m 2 . Hirai et al [14] calculated the temperature distribution of a tungsten-based PFM under HHF.…”

Section: Introductionmentioning

confidence: 99%

Thermal Shock Behavior Analysis of Tungsten-Armored Plasma-Facing Components for Future Fusion Reactor

Wang

et al. 2018

Acta Metall. Sin. (Engl. Lett.)

View full text Add to dashboard Cite

In a fusion reactor, plasma-facing components (PFCs) will suffer severe thermal shock; behavior and performance of PFCs under high heat flux (HHF) loads are of major importance for the long-term stable operation of the reactor. This work investigates the thermo-mechanical behaviors of tungsten armor under high heat loads by the method of finite element modeling and simulating. The temperature distribution and corresponding thermal stress changing rule under different HHF are analyzed and deduced. The Manson-Coffin equation is employed to evaluate the fatigue lifetime (cyclic times of HHF loading) of W-armored first wall under cyclic HHF load. The results are useful for the formulation design and structural optimization of tungsten-armored PFCs for the future demonstration fusion reactor and China fusion experimental thermal reactor.

show abstract

“…During the past decade, researchers performed a considerable amount of work on the experimental tests and finite element (FEM) simulations to examine the performances of FW under heat flux and neutron with SS316LN as a structural material [4][5][6][7][8][9][10][11][12][13][14][15][16][17][18][19]. Hatano et al [3] examined the integrity of the HIP bonded interface, fatigue life time, and fracture behavior of the panel.…”

Section: Introductionmentioning

confidence: 99%

“…You and Bolt [4] calculated the temperature and stress distributions for plasma facing materials with heat load of 5.0 MW/m 2 and duration time of 10 s. Cardella et al [5] calculated and analyzed the temperature and stress of FW under the average heat flux was 0.5 MW/m 2 and neutron load was 1.19 MW/m 3 . Dell'Orco et al [6] presented a thermal-mechanical calculation for FW mock-ups under a heat flux of 0.8 MW/m 2 . Recently, Lee et al [8,9] investigated HIP bonded Be/Cu/SS mock-ups for the FW under high heat flux conditions (1.5 and 2.0 MW/m 2 ); only surface heat flux load and water cooling were considered.…”

Section: Introductionmentioning

confidence: 99%