Impact of material system thermomechanics and thermofluid performance on He-cooled ceramic breeder blanket designs with SiCf/SiC

نویسندگان

  • Alice Y. Ying
  • Takehiko Yokomine
  • Akihiko Shimizu
  • Mohamed Abdou
  • Akira Kohyama
چکیده

This paper presents results from a recent effort initiated under the JUPITER-II collaborative program for high temperature gas-cooled blanket systems using SiCf /SiC as a structural material. Current emphasis is to address issues associated with the function of the helium gas considered in the DREAM and ARIES-I concepts by performing thermomechanical and thermofluid analysis. The objective of the analysis is to guide future research focus for a task in the project. It is found that the DREAM concept has the advantage of achieving uniform temperature without threatening blanket pebble bed integrity by differential thermal stress. However, its superiority needs to be further justified by investigating the feasibility and economic issues involved in the tritium extraction technology. 2004 Elsevier B.V. All rights reserved.

برای دانلود رایگان 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

An overview of dual coolant Pb–17Li breeder first wall and blanket concept development for the US ITER-TBM design

An attractive blanket concept for the fusion reactor is the dual coolant Pb–17Li liquid (DCLL) breeder design. Reduced activation ferritic steel (RAFS) is used as the structural material. Helium is used to cool the first wall and blanket structure, and the self-cooled breeder Pb–17Li is circulated for power conversion and for tritium breeding. A SiCf/SiC composite insert is used as the magnetoh...

متن کامل

Neutronics Analysis of A Self-Cooled Blanket for A Laser Fusion Plant with Magnetic Diversion

A blanket concept made of the low electrical conductivity SiCf/SiC composite and utilizing Li17Pb83 as coolant and tritium breeder has been developed and integrated with the magnetic diversion system. Neutronics issues related to tritium breeding adequacy particularly with the area lost to the dump plates at the ring and point cusps were addressed. Radiation damage and lifetime considerations f...

متن کامل

High performance blanket for ARIES-AT power plant

The ARIES-AT blanket has been developed with the overall objective of achieving high performance while maintaining attractive safety features, simple design geometry, credible maintenance and fabrication processes, and reasonable design margins as an indication of reliability. The design is based on Pb–17Li as breeder and coolant and SiCf/SiC composite as structural material. This paper summari...

متن کامل

US Plans and Strategy for ITER Blanket Testing

Testing blanket concepts in the integrated fusion environment is one of the principal objectives of ITER. Blanket test modules will be inserted in ITER from Day 1 of its operation and will provide the first experimental data on the feasibility of the D-T cycle for fusion. With the US rejoining ITER, the US community has decided to have strong participation in the ITER Test Blanket Module (TBM) ...

متن کامل

Transient flow behavior for a hel ium-cooled ceramic breeder blanket *

This paper presents a thermal-hydraulic analysis of a helium-cooled ceramic breeder blanket for the ITER. It is found that the blanket can operate at moderate pressure and temperatures, which coupled to the use of an inert gas, makes it particularly attractive from a safety standpoint. Transient analysis of the manifolding flow distribution indicates that the introduction of a diffusive plate a...

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

عنوان ژورنال:

دوره   شماره 

صفحات  -

تاریخ انتشار 2004