Exploring the Engineering Performance Limits of DNB
Creators
- 1. ITER-India, Institute for Plasma Research, Gandhinagar (India)
- 2. ITER Organisation, St Paul Lez Durance (France)
Description
Full text: Amongst the two Neutral Beam systems for ITER, the Diagnostic Neutral Beam (DNB) system has a special operational mandate to provide a 100 keV, ∼ 20 A beam to ITER, with a modulation frequency of 5 Hz having duty cycle of 3 s ON — 20 s OFF for 3600 s. The modulation of beam is realised by the application of modulating acceleration and extraction voltage levels; thereby leading to a modulation of power density incident on the beam facing heat flux receiving components — accelerator & electron dumps system, neutraliser, residual ion dump (RID), calorimeter, exit scraper and duct liner. The design requirements have been generated taking into consideration the ITER needs and engineering design of these components has been carried out considering modulated high heat flux and the corresponding thermal hydraulic engineering. Different scenarios such as operational, test, handling, emergency and faulted conditions are considered and the analysis have been performed by FEA software- ANSYS. Both monotonic as well as cycle type structural damage verifications were performed using ITER SDC-IC. Final designs of all components have been arrived at after different stress intensities conformed to the criterion levels of SDC-IC. The BTP specifications for DNB components take into account this conformity and incorporate adequate safety margin. While this design meets the requirements of the mandate for DNB, there is a need to assess the limits of operation of DNB in terms of the following: 1. The maximum length of time, beyond 3 s for with the modulation can be sustained. 2. The maximum pulse length for which the beam can be operated without modulation. These inputs will help CXRS, BES diagnosticians to design their diagnostic setup for the maximum level of performance. The performance characterisation of DNB to be carried out in the Indian-Test Facility (INTF), which include provisions to tests those above mentioned limits. The paper presents the results of assessments that have been carried out and provides recommendations for the maximum operation limits. (author)
Additional details
Publishing Information
- Imprint Title
- 24. IAEA Fusion Energy Conference. Programme and Book of Abstracts
- Imprint Pagination
- 789 p.
- Journal Page Range
- p. 635
- Report number
- IAEA-CN--197
Conference
- Title
- 24. IAEA Fusion Energy Conference
- Acronym
- FEC 2012
- Dates
- 8-13 Oct 2012
- Place
- San Diego, CA (United States)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 45034054
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCELERATORS; ACCIDENTS; BEAMS; CALORIMETERS; COMPUTER CODES; DESIGN; ELECTRIC POTENTIAL; ELECTRONS; HEAT FLUX; ITER TOKAMAK; KEV RANGE; MODULATION; PERFORMANCE; POWER DENSITY; SAFETY MARGINS; TEST FACILITIES; THERMAL HYDRAULICS
- Descriptors DEC
- CLOSED PLASMA DEVICES; ELEMENTARY PARTICLES; ENERGY RANGE; FERMIONS; FLUID MECHANICS; HYDRAULICS; LEPTONS; MEASURING INSTRUMENTS; MECHANICS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Secondary number(s)
- ITR/P5--43