Published October 2011 | Version v1
Journal article

Thermo-hydraulic design verification of the neutral beam liner for the ITER vacuum vessel

  • 1. Electro-Mechanical Research Institute, Hyundai Heavy Industries Co. Ltd., 102-18 Mabuk-dong, Giheung-gu, Yongin-si, Gyeonggi-do 446-716 (Korea, Republic of)
  • 2. National Fusion Research Institute, 113 Gwahangno, Yuseong-gu, Daejeon-si 305-333 (Korea, Republic of)

Description

The ITER vacuum vessel has upper, equatorial and lower port structures used for equipment installation, utility feedthroughs, vacuum pumping and access inside the vessel for maintenance. A neutral beam (NB) port of equatorial ports provides a path of neutral beam for plasma heating and current drive. An internal duct liner is built in the NB ports, and copper alloy panels are placed in the top and bottom of the liner to protect duct surface from high-power heat loads. Global NB liner models for the upper panel and the lower panel have been developed, and flow field and conjugate heat transfer analyses have been performed to find out pressure drop and heat transfer characteristics of the liner. Heat loads such as NB power, volumetric heating and surface heat flux are applied in the analyses for beam steering and misalignment conditions. For the upper panel, it is found that unbalanced flow distribution occurs in each flow path, and this causes poor heat transfer performance as well. In order to improve flow distribution and to reduce pressure losses, hydraulic analyses for modified cooling path schemes have been carried out, and design recommendations are made based on the analysis results. For the lower panel, local flow distributions and pressure drop values at each header and branch of the tube are obtained by applying design coolant flow rate. Together with the coolant flow field, temperature and heat transfer coefficient distributions are also acquired from the analyses. Based on the analysis results, it is concluded that the lower panel for the NB liner is relatively well designed even though the given heat loads are very severe.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2010.12.043

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2010.12.043;
PII
S0920-3796(10)00578-8;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
86
Journal Issue
9-11
Journal Page Range
p. 1971-1974
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
26. symposium on fusion technology
Acronym
SOFT-26
Dates
27 Sep - 1 Oct 2010
Place
Porto (Portugal)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
43067996
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BEAM INJECTION HEATING; CONTAINERS; DESIGN; HEAT TRANSFER; HEATING LOAD; ITER TOKAMAK; LINERS; NEUTRAL ATOM BEAM INJECTION; PRESSURE DROP; THERMAL HYDRAULICS; VERIFICATION
Descriptors DEC
BEAM INJECTION; CLOSED PLASMA DEVICES; ENERGY TRANSFER; FLUID MECHANICS; HEATING; HYDRAULICS; MECHANICS; PLASMA HEATING; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Copyright
Copyright (c) 2010 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.