Experimental and analytical studies on thermal-hydraulic performance of a vacuum vessel pressure suppression system in ITER
Creators
- 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)
Files
35072360.pdf
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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