Engineering design and analysis of Indian LLCB TBM set
Creators
- 1. Institute for Plasma Research, Bhat, Gandhinagar 382428, Gujarat (India)
- 2. Bhabha Atomic Research Centre, Trombay, Mumbai 400085 (India)
Description
India is developing Lead Lithium cooled Ceramic Breeder (LLCB) Test Blanket Module (TBM) for testing in ITER for the validation of fusion blanket design tools, tritium breeding performance and high grade heat extraction capability relevant to Indian DEMO. LLCB TBM is designed to withstand various ITER loads and its combinations, like thermal, mechanical including the high pressure coolant loads, electromagnetic loads during plasma disruption and seismic loading conditions. LLCB TBM system is designed in compliance with ITER Safety requirements and guidelines. A few challenging part in the design includes the design of helium cooled First Wall (FW) and back plates, the attachment system between TBM and the shield block to withstand loads for all the ITER operational modes, routing of high temperature process pipes between TBM and the shield block, interfaces between process pipes and the connecting flange, design of manifolds of different process fluids etc. Analysis has been performed on the LLCB TBM set using a Finite Element code, ANSYS. Relevant codes and standards, namely the French code RCC-MR, has been followed for the design analysis. The details of the analysis and further plans and proposals for improvement in design will be discussed in this paper.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2015.11.018Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2015.11.018;
- PII
- S0920-3796(15)30343-4;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 109-111
- Journal Issue
- Part B
- Journal Page Range
- p. 1581-1586
- ISSN
- 0920-3796
- CODEN
- FEDEEE
Conference
- Title
- 12. international symposium on fusion nuclear technology
- Acronym
- ISFNT-12
- Dates
- 14-18 Sep 2015
- Place
- Jeju Island (Korea, Republic of)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48071550
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BREEDING BLANKETS; CERAMICS; DYNAMIC LOADS; FINITE ELEMENT METHOD; FIRST WALL; HEAT EXTRACTION; HELIUM; INDIA; ITER TOKAMAK; LEAD; LITHIUM; SAFETY STANDARDS; SEISMIC EFFECTS; SHIELDS; STATIC LOADS; TEMPERATURE RANGE 0400-1000 K; TEST FACILITIES; TRITIUM; VALIDATION
- Descriptors DEC
- ALKALI METALS; ASIA; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CALCULATION METHODS; CLOSED PLASMA DEVICES; DEVELOPING COUNTRIES; ELEMENTS; FLUIDS; GASES; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; MATHEMATICAL SOLUTIONS; METALS; NONMETALS; NUCLEI; NUMERICAL SOLUTION; ODD-EVEN NUCLEI; RADIOISOTOPES; RARE GASES; REACTOR COMPONENTS; STANDARDS; TEMPERATURE RANGE; TESTING; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; YEARS LIVING RADIOISOTOPES
Optional Information
- Copyright
- Copyright (c) 2015 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.