DESIGN, ANALYSIS AND TEST CONCEPT FOR PROTOTYPE CRYOLINE OF ITER
- 1. Institute for Plasma Research Bhat, Gandhinagar, Gujarat, 382428 (India)
Description
The ITER cryo-distribution and cryoline is a part of the in-kind supply for India. The design of the systems is in progress. The topology of torus and neutral beam cryoline is defined as six process pipes along with thermal shield at 80 K and outer vacuum jacket. In order to develop confidence in the concept and to establish the high level of engineering and manufacturing technology, a prototype testing has been proposed. The prototype test will be carried out on 1:1 model in terms of dimension. However, the mass flow rate of the supercritical helium at 4.5 K and gaseous helium at 80 K will be on a 1:10 scale. The prototype cryoline has been designed and analyzed for thermal, structural and hydraulic parameters. The objective of this prototype test is to verify mechanical behavior due to thermal stress and pressure force, thermal and hydraulic performances. The concept of test facility has been realized along with the Piping and Instrumentation (P and I) diagram, instrumentation, controls, data acquisition, 80 K helium generation system along with supply and return valve boxes and interfacing hardware. The design concept, methodology for analysis and results, as well as the test facility have been discussed
Additional details
Identifiers
- DOI
- 10.1063/1.2908542;
Publishing Information
- Journal Title
- AIP Conference Proceedings
- Journal Volume
- 985
- Journal Issue
- 1
- Journal Page Range
- p. 1716-1723
- ISSN
- 0094-243X
- CODEN
- APCPCS
Conference
- Title
- Advances in cryogenic engineering
- Acronym
- Cryogenic Engineering Conference - CEC
- Dates
- 16-20 Jul 2007
- Place
- Chattanooga, TN (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 40017530
- Subject category
- S71: CLASSICAL AND QUANTUM MECHANICS, GENERAL PHYSICS; S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTROL; CRYOGENICS; DESIGN; FLOW RATE; HELIUM; ITER TOKAMAK; MANUFACTURING; PERFORMANCE TESTING; SUPERCONDUCTING MAGNETS; TEST FACILITIES; THERMAL HYDRAULICS; THERMAL SHIELDS; THERMAL STRESSES; VALVES
- Descriptors DEC
- CLOSED PLASMA DEVICES; CONTROL EQUIPMENT; ELECTRICAL EQUIPMENT; ELECTROMAGNETS; ELEMENTS; EQUIPMENT; FLOW REGULATORS; FLUID MECHANICS; FLUIDS; GASES; HYDRAULICS; MAGNETS; MECHANICS; NONMETALS; RARE GASES; SHIELDS; STRESSES; SUPERCONDUCTING DEVICES; TESTING; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Notes
- (c) 2008 American Institute of Physics