Thermal-hydraulic performance analysis for the conceptual design of Korean HCCR TBMset
Creators
- 1. KAERI, Daejeon (Korea, Republic of)
- 2. Gentec Co., Daejeon (Korea, Republic of)
- 3. National Fusion Research Institute, Daejeon (Korea, Republic of)
Description
The purpose of this document is to provide the thermal-hydraulic (TH) analyses results of the Helium Cooled Ceramic Reflector (HCCR) Test Blanket Module (TBM) including TBM-shield, which is called TBM-set. The analyses were performed for Electro- Magnetic Module (EM-TBM) and INTegral Module (INT-TBM) including TBM-shield, respectively, with the same model and meshes according to the ITER operation conditions of H/He and D-T phases, respectively. Thermal-hydraulic performance of the EM- and INTTBM- sets were analysed using the fixed CATIA model for CDR. Fine mesh with 15.9 million elements for solid and 44.7 million elements for fluid was used for ANSYS-CFX 14.5 simulation and coarse mesh with 7.6 million elements for solid is prepared for the thermomechanical analysis. The boundary conditions such as heat flux, nuclear heating, and coolant conditions were determined considering the ITER operation condition and designed cooling scheme. The analysis results and conclusions are as follows; (1) It is confirmed that both EM- and INT-TBM performance results meet the design requirements, which were determined by the material characteristics. (2) The temperature results with fine mesh of both EMand INT-TBM-sets were successfully transferred to those of coarse mesh for the thermo-mechanical analysis
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS 2015 spring meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [3 p.]
Conference
- Title
- 2015 spring meeting of the KNS
- Dates
- 6-8 May 2015
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 47023458
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- DESIGN; FLOW RATE; ITER TOKAMAK; PERFORMANCE; PRESSURE DROP; THERMAL HYDRAULICS
- Descriptors DEC
- CLOSED PLASMA DEVICES; FLUID MECHANICS; HYDRAULICS; MECHANICS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Notes
- 6 refs, 5 figs, 1 tab