Numerical Simulation Analysis for the Divertor Plate of DEMO Reactor

نویسندگان

  • Changle. Liu
  • Kenji. Tobita
چکیده

The hydraulic simulation and structure coupled analysis were used to explore critical heat flux (CHF) margin of the W (tungsten) armour and the accommodation of the thermal stress between the cooling tube and the W armour. The t (wall thickness of the F82H tube) variation or as a constant were considered to analysis the heat removal capability of the cooling tube. It was found a nonlinear distribution of the peak T (temperature) for the W armour and the top cooling tube with the tube bore rising. And an allowable heat flux with 5 MW/m or under the value would be acceptable based on present engineering consideration ( t=1mm, d=10mm and the coolant velocity=10m/s). The structure coupled analysis (d=10mm) indicated the primary stress of the cooling tube was safety, less than 50MPa, but thermal stress would be closed to 3Sm (F82H,550 ) due to the thermal expansion between W armour and F82H tube. Based on the coupled results, a thinner tube would be better than a thicker one by considering thermal conducting and thermal stress. Finally, for the issues on CHF and thermal stress, the possible optimizations were discussed involved the material choice, the structure of the cooling channel and the water condition .

برای دانلود متن کامل این مقاله و بیش از 32 میلیون مقاله دیگر ابتدا ثبت نام کنید

ثبت نام

اگر عضو سایت هستید لطفا وارد حساب کاربری خود شوید

منابع مشابه

Simulation of Power Exhaust in Edge and Divertor of the SlimCS Tokamak Demo Reactor

Design of the power handling for the demo tokamak reactor, SlimCS, with the fusion power of Pfus ≤ 3 GW and the exhausted power of Pout = 500 MW was investigated. First, effects of the divertor geometry of the V-shaped corner and the Ar impurity seeding on the radiation distribution and the target power loading were summarized in the simulation (SOLDOR/NEUT2D) with a constant concentration of A...

متن کامل

Analysis of sweeping heat loads on divertor plate materials

The heat flux on the divertor plate of a fusion reactor is probably one of the most limiting constraints on its lifetime. The current heat flux profile on the outer divertor plate of a device like the International Thermonuclear Experimental Reactor (ITER) is highly peaked with narrow profile. The peak heat flux can be as high as 30-40 MW/m 2 with full width at half maximum (FWHM) of the order ...

متن کامل

Divertor Design Study on Compact DEMO Reactor for Handling of Huge Exhaust Power

For the divertor design study of a compact DEMO reactor, Slim CS, using SOLDOR/NEUT2D code, we estimated a prospect of handling huge exhausted power in the divertor. Assuming the exhausted power of 500 MW and ion out flux of 0.5x10 23 s -1 into the scrape-off-layer, the peak heat load is estimated to be 70 MW/m 2 on the outer target on the initial divertor design (vertical target). This value e...

متن کامل

Present Status of Integrated Performance Achieved in Tokamak Experiments and Critical Issues Towards DEMO Reactor

This paper reports the present status of the integrated performance achieved in tokamak experiments and critical issues towards DEMO reactor. The achieved integrated performance towards DEMO reactor is visualized using by introducing the radar-screen diagram with the normalized performance. The normalized plasma parameters foreseen in DEMO have been developed experimentally in world-wide, but t...

متن کامل

Beryllium and graphite performance in ITER during a disruption *

Plasma disruptions are considered one of the most limiting factors for successful operation of magnetic fusion reactors. During a disruption, a sharp, rapid release of energy strikes components such as the divertor or limiter plates. Severe surface erosion and melting of these components may then occur. The amount of material eroded from both ablation and melting is important to the reactor des...

متن کامل

ذخیره در منابع من


  با ذخیره ی این منبع در منابع من، دسترسی به آن را برای استفاده های بعدی آسان تر کنید

برای دانلود متن کامل این مقاله و بیش از 32 میلیون مقاله دیگر ابتدا ثبت نام کنید

ثبت نام

اگر عضو سایت هستید لطفا وارد حساب کاربری خود شوید

عنوان ژورنال:

دوره   شماره 

صفحات  -

تاریخ انتشار 2010