First Wall Lifetime Extension with Flowing Liquid Zone for Fusion Reactors
Description
Full text: In this work, different structural materials were subject of investigation. The calculations are conducted for a fusion power generation of 1 GWel over thirty years of reactor operation with a thermos-dynamical conversion efficiency of 35% leading to 2.857 GWth by a capacity factor of 100%. The structural material should have the properties given briefly as below: • Low neutron absorption cross sections. • Adequate mechanical properties before and after irradiation. • Operation at a wide temperature window. • Working at high temperatures. • Resistant to atomic displacement and helium generation damage. • Low activation property under 14 MeV neutrons. • High thermal conductivity. One of the candidates as structural material is the oxide dispersed steel (ODS). At first, a fusion-fission (hybrid) with a multilayered spherical blanket has been investigated, which is composed of a first wall made of oxide dispersed steel (ODS, 2 cm); neutron multiplier and coolant zone made of LiPb; ODS-separator (2 cm); a molten salt Flibe coolant and fission zone; ODS-separator (2 cm); graphite reflector. In the second phase, LiPb coolant zone behind the first wall has been removed. But instead, a flowing liquid protective first wall is included in front of the solid first wall in order to reduce material damage and residual radioactivity after final disposal of the latter. SS-304 type steel, SiC and graphite were also selected as structural materials of a magnetic fusion energy (MFE) reactor. Different types of liquid coolant with tritium breeding capabilities (FLIBE, Li17Pb83, natural lithium, all with natural lithium component) are investigated to protect the first wall from neutron- and bremsstrahlung radiation and fusion reaction debris. (author)
Additional details
Identifiers
Publishing Information
- Imprint Title
- 26. IAEA Fusion Energy Conference. Programme, Abstracts and Conference Material
- Imprint Pagination
- 935 p.
- Journal Page Range
- p. 767
- Report number
- IAEA-CN--234
Conference
- Title
- 26. IAEA Fusion Energy Conference
- Acronym
- FEC 2016
- Dates
- 17-22 Oct 2016
- Place
- Kyoto (Japan)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 50012666
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BREMSSTRAHLUNG; FIRST WALL; GRAPHITE; INTERSTITIAL HELIUM GENERATION; LIFETIME EXTENSION; LITHIUM; NEUTRONS; SILICON CARBIDES; STEELS; THERMAL CONDUCTIVITY; THERMONUCLEAR REACTIONS; THERMONUCLEAR REACTORS; TRITIUM
- Descriptors DEC
- ALKALI METALS; ALLOYS; BARYONS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CARBIDES; CARBON; CARBON ADDITIONS; CARBON COMPOUNDS; ELECTROMAGNETIC RADIATION; ELEMENTARY PARTICLES; ELEMENTS; FERMIONS; HADRONS; HYDROGEN ISOTOPES; IRON ALLOYS; IRON BASE ALLOYS; ISOTOPES; LIFETIME; LIGHT NUCLEI; METALS; MINERALS; NONMETALS; NUCLEAR REACTIONS; NUCLEI; NUCLEONS; NUCLEOSYNTHESIS; ODD-EVEN NUCLEI; PHYSICAL PROPERTIES; PHYSICAL RADIATION EFFECTS; RADIATION EFFECTS; RADIATIONS; RADIOISOTOPES; SERVICE LIFE; SILICON COMPOUNDS; SYNTHESIS; THERMODYNAMIC PROPERTIES; THERMONUCLEAR REACTOR WALLS; TRANSITION ELEMENT ALLOYS; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- Abstract only
- Secondary number(s)
- IAEA-CN--234-0028