Published September 2003 | Version v1
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Experimental and analytical studies on thermal-hydraulic performance of a vacuum vessel pressure suppression system in ITER

  • 1. Japan Atomic Energy Research Institute, Tokai-mura, Ibaraki-ken (Japan)
  • 2. Japan Atomic Energy Research Institute, Tokai-mura, Ibaraki-ken (JP)

Description

An integrated ICE (Ingress-of-Coolant Event) test facility was constructed to demonstrate that the ITER (International Thermonuclear Experimental Reactor) safety design approach and design parameters for the ICE are adequate. Major objectives of the integrated ICE test facility are to estimate the performance of an integrated pressure suppression system and obtain the validation data for safety analysis codes and clarify the two-phase flow behavior under vacuum. The integrated ICE test facility simulates the ITER components with a scaling factor of 1/1600. The modified TRAC-PF1 code is used to verify the integrated ICE experimental results. From the present study the effectiveness of the ITER pressure suppression system was verified experimentally and analytically, and then, it was clarified quantitatively that the prediction accuracy of the modified TRAC-PF1 code is very high. (author)

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Part of:
Fusion energy 2002. 19th conference proceedings

Additional details

Publishing Information

Imprint Title
Fusion energy 2002. 19th conference proceedings
Imprint Pagination
516 p.
Journal Issue
no. 19/CD
Series
C and S papers series
Journal Page Range
[5 p.]
ISSN
1562-4153
Report number
IAEA-CSP--19/CD

Conference

Title
19. IAEA fusion energy conference
Dates
14-19 Oct 2002
Place
Lyon (France)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
35072360
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTERIZED SIMULATION; DESIGN; ITER TOKAMAK; PERFORMANCE; PRESSURE SUPPRESSION; PRESSURE VESSELS; SAFETY; SAFETY ANALYSIS; SCALING LAWS; T CODES; TEST FACILITIES; TWO-PHASE FLOW; VALIDATION
Descriptors DEC
CLOSED PLASMA DEVICES; COMPUTER CODES; CONTAINERS; FLUID FLOW; SIMULATION; TESTING; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Notes
6 refs, 6 figs Imprint:Data in PDF format
Secondary number(s)
SE/P--02