Published October 2021 | Version v1
Journal article

Status of HCCR TBM program for DEMO blanket

  • 1. Korea Institute of Fusion Energy, Daejeon (Korea, Republic of)
  • 2. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

Highlights: • The main functions and design concepts of the HCCR breeding blanket are to be verified in ITER through the HCCR Test Blanket Module (TBM) program. • R&D activities for the HCCR TBM program in the fields of structural and breeder material, TBM set fabrication technology, tritium extraction technology, and helium cooling technology were introduced. • The maximum operating temperature and pressure conditions and thermal properties of Li2TiO3 were determined by investigating the sintering phenomena and pebble degradation. • The capability of absorption and desorption of hydrogen isotopes was investigated in the cryogenic molecular sieves adopted in the TES. . • The performance curves (characteristics) of the circulator obtained with the pressure ratio data were well grouped according to the corrected speed and the corrected mass flow rate under the reference conditions of 80 bar and a 50 °C helium flow. Development of the Helium Cooled Ceramic Reflector (HCCR) breeding blanket is underway according to the development strategy of core technology for K-DEMO under the fusion energy development roadmap in Korea. The main goals are to validate integrated design tools and to develop core technologies in the field of materials, manufacturing and joining technologies, helium cooling and tritium technologies, system integration, and safety technologies. A unique graphite reflector concept was adopted to save cost by reducing the amount of beryllium neutron multiplier. The main functions and design concepts of the HCCR breeding blanket are to be verified in ITER through the HCCR Test Blanket Module (TBM) program. Not only breeder modules are to be tested in ITER but also the technologies of cooling, coolant purification, tritium extraction, etc. are to be tested or proved in ITER before employed in DEMO. This paper introduces the current updates of the design and R&D activities of the HCCR TBM systems in the preliminary design stage.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2021.112553

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2021.112553;
PII
S092037962100329X;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
171
Journal Page Range
vp.
ISSN
0920-3796
CODEN
FEDEEE

Optional Information

Copyright
Copyright (c) 2021 Elsevier B.V. All rights reserved.