Published March 5, 1992 | Version v1
Report Restricted

Numerical simulation of the stability in long cable-in-conduit conductors for fusion magnets

  • 1. Wisconsin Univ., Madison, WI (United States). Dept. of Nuclear Engineering and Engineering Physics
  • 2. Lawrence Livermore National Lab., CA (United States)

Description

The stability phenomenon is investigated numerically for a quench initiating in a cable-in-conduit conductor (CICC) at a significant distance from the ends. The thermo-hydraulic computer program, CICC, was used. The geometry chosen for this study is a toroidal field (TF) coil for the conceptual design activity (CDA) of the International Thermonuclear Experimental Reactor (ITER). Previous studies of short conductors have shown that convective helium flows, induced by the initiating heat pulse, control the stability of the conductor. The present study of a long conductor exhibits reduced energy margins and the absence of a transition region between the well-cooled and ill-cooled stability regions because the initiating heat pulse has difficulty sustaining a convective flow. The effect of heat-pulse duration and heated length were considered. For short, high-energy heat pulses, high convective and conductive heat-transfer coefficients can only be mismatched for 10 ms. If the heat-pulse energy is spread your 100 ms, the steady-state heat-transfer coefficient is sufficient to stabilize the conductor. Pulse durations between 10 and 100 ms cause a decrease in energy margin. On the other hand, the conductor length heated was found to have only a small effect on stability. 3 refs

Availability note (English)

MF available from INIS under the Report Number; OSTI as DE92012694; NTIS; INIS; US Govt. Printing Office Dep.

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Additional details

Publishing Information

Imprint Pagination
6 p.
Report number
UCRL-JC--109337

Conference

Title
10. topical meeting on technology of fusion energy.
Dates
7-12 Jun 1992.
Place
Boston, MA (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
23069294
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
C CODES; COMPUTERIZED SIMULATION; ELECTRIC CONDUCTORS; HEAT TRANSFER; HYDRAULICS; ITER TOKAMAK; MAGNET COILS; MAGNETS; STABILITY
Descriptors DEC
CLOSED PLASMA DEVICES; COMPUTER CODES; ELECTRIC COILS; ELECTRICAL EQUIPMENT; ENERGY TRANSFER; EQUIPMENT; SIMULATION; THERMONUCLEAR DEVICES; TOKAMAK DEVICES

Optional Information

Contract/Grant/Project number
Contract W-7405-ENG-48
Funding organization
USDOE, Washington, DC (United States).
Secondary number(s)
CONF-920607--13.