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.2021.112553Additional 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
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54004310
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S36: MATERIALS SCIENCE;
- Descriptors DEI
- ABSORPTION; ALLOYS; BREEDING BLANKETS; CERAMICS; COOLANTS; CRYOGENICS; DESIGN; DESORPTION; FLOW RATE; GRAPHITE; HELIUM; ITER TOKAMAK; LITHIUM TITANATES; MATERIALS; MOLECULAR SIEVES; NEUTRONS; PURIFICATION; THERMODYNAMIC PROPERTIES; TRITIUM
- Descriptors DEC
- ADSORBENTS; ALKALI METAL COMPOUNDS; BARYONS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CARBON; CLOSED PLASMA DEVICES; ELEMENTARY PARTICLES; ELEMENTS; FERMIONS; FLUIDS; GASES; HADRONS; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; LITHIUM COMPOUNDS; MINERALS; NONMETALS; NUCLEI; NUCLEONS; ODD-EVEN NUCLEI; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; RADIOISOTOPES; RARE GASES; REACTOR COMPONENTS; SORPTION; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TITANATES; TITANIUM COMPOUNDS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; TRANSITION ELEMENT COMPOUNDS; YEARS LIVING RADIOISOTOPES
Optional Information
- Copyright
- Copyright (c) 2021 Elsevier B.V. All rights reserved.