Published May 2015 | Version v1
Miscellaneous

Thermal-hydraulic performance analysis for the conceptual design of Korean HCCR TBMset

  • 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

Part of:
Proceedings of the KNS 2015 Spring Meeting

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