A helium-cooled blanket design of the low aspect ratio reactor Metadata

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Title

  • Main Title A helium-cooled blanket design of the low aspect ratio reactor

Creator

  • Author: Wong, C.P.
    Creator Type: Personal
  • Author: Baxi, C.B.
    Creator Type: Personal
  • Author: Reis, E.E.
    Creator Type: Personal
    Creator Info: General Atomics, San Diego, CA (United States)
  • Author: Cerbone, R.
    Creator Type: Personal
  • Author: Cheng, E.T.
    Creator Type: Personal
    Creator Info: TSI Research, Solana Beach, CA (United States)

Contributor

  • Sponsor: United States. Department of Energy. Office of Energy Research.
    Contributor Type: Organization
    Contributor Info: USDOE Office of Energy Research, Washington, DC (United States)

Publisher

  • Name: General Atomic Company
    Place of Publication: San Diego, California
    Additional Info: General Atomics, San Diego, CA (United States)

Date

  • Creation: 1998-03-01

Language

  • English

Description

  • Content Description: An aggressive low aspect ratio scoping fusion reactor design indicated that a 2 GW(e) reactor can have a major radius as small as 2.9 m resulting in a device with competitive cost of electricity at 49 mill/kWh. One of the technology requirements of this design is a high performance high power density first wall and blanket system. A 15 MPa helium-cooled, V-alloy and stagnant LiPb breeder first wall and blanket design was utilized. Due to the low solubility of tritium in LiPb, there is the concern of tritium migration and the formation of V-hydride. To address these issues, a lithium breeder system with high solubility of tritium has been evaluated. Due to the reduction of blanket energy multiplication to 1.2, to maintain a plant Q of > 4, the major radius of the reactor has to be increased to 3.05 m. The inlet helium coolant temperature is raised to 436 C in order to meet the minimum V-alloy temperature limit everywhere in the first wall and blanket system. To enhance the first wall heat transfer, a swirl tape coolant channel design is used. The corresponding increase in friction factor is also taken into consideration. To reduce the coolant system pressure drop, the helium pressure is increased from 15 to 18 MPa. Thermal structural analysis is performed for a simple tube design. With an inside tube diameter of 1 cm and a wall thickness of 1.5 mm, the lithium breeder can remove an average heat flux and neutron wall loading of 2 and 8 MW/m(2), respectively. This reference design can meet all the temperature and material structural design limits, as well as the coolant velocity limits. Maintaining an outlet coolant temperature of 650 C, one can expect a gross closed cycle gas turbine thermal efficiency of 45%. This study further supports the use of helium coolant for high power density reactor design. When used with the low aspect ratio reactor concept a competitive fusion reactor can be projected at 51.9 mill/kWh.
  • Physical Description: 25 p.

Subject

  • Keyword: Thermonuclear Reactors
  • Keyword: Thermonuclear Reactor Cooling Systems
  • Keyword: Breeding Blankets
  • STI Subject Categories: 70 Plasma Physics And Fusion
  • Keyword: First Wall
  • Keyword: Lithium
  • Keyword: Design
  • Keyword: Thermal Analysis
  • Keyword: Vanadium Alloys
  • Keyword: Aspect Ratio
  • Keyword: Wall Loading

Source

  • Conference: International Atomic Energy Agency Technical Committee meeting on fusion power plant design, Culham (United Kingdom), 24-27 Mar 1998

Collection

  • Name: Office of Scientific & Technical Information Technical Reports
    Code: OSTI

Institution

  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Article

Format

  • Text

Identifier

  • Other: DE98005690
  • Report No.: GA--A22828
  • Report No.: CONF-980374--
  • Grant Number: AC03-98ER54411
  • Office of Scientific & Technical Information Report Number: 672069
  • Archival Resource Key: ark:/67531/metadc705764

Note

  • Display Note: INIS; OSTI as DE98005690