Microstructure evolution and deuterium permeation behavior of CLF-1 steel under Li4SiO4 tritium breeder corrosion cycles DOI

Hongzhihao,

Wanglong,

Fantao Meng

и другие.

Corrosion Science, Год журнала: 2024, Номер unknown, С. 112658 - 112658

Опубликована: Дек. 1, 2024

Язык: Английский

Molten LiF additive promoted low‐temperature densification in sintering Li2TiO3 ceramic pebbles DOI

Guangfan Tan,

Shuai Li,

Shouxi Gu

и другие.

Journal of the American Ceramic Society, Год журнала: 2025, Номер unknown

Опубликована: Апрель 9, 2025

Abstract Li 2 TiO 3 ceramics are promising for tritium breeding applications in nuclear fusion energy considering the chemical inertness and release performance. To solve synthesis problems of pebbles (including lithium loss at high‐temperature, microstructure coarsening, poor mechanical properties), alkaline metal halides incorporated to fabricate ceramic with good Besides, this study provides an in‐depth investigation into how additive influences shrinkage, internal structural evolution, grain size, crushing load pebbles. Compared LiCl, addition LiF can obviously reduce particle size increase relative density samples a lower sintering temperature. Meanwhile, results show that breeder sintered 950°C have optimal properties, including 1.68 µm average 92.9% density, excellent 140.8 N, which superior over those obtained through traditional methods. it also exhibits structure stability types deuterium released D O HTO, respectively. This research not only facilitates low‐temperature densification but guides design pebbles, offers potential enhancing service performance materials within reactor blankets.

Язык: Английский

Процитировано

0

Tritium release performance of biphasic Li2TiO3–Li4SiO4 ceramic pebbles fabricated by centrifugal granulation method DOI

Guangfan Tan,

Qilai Zhou, Xin Hu

и другие.

Ceramics International, Год журнала: 2024, Номер 50(17), С. 31225 - 31234

Опубликована: Май 28, 2024

Язык: Английский

Процитировано

3

Study of Gas Swelling Processes under Irradiation with Protons and He2+ Ions in Li4SiO4–Li2TiO3 Ceramics DOI Creative Commons
Inesh Kenzhina, Аrtem L. Kozlovskiy, Yevgen Chikhray

и другие.

Crystals, Год журнала: 2023, Номер 13(10), С. 1526 - 1526

Опубликована: Окт. 22, 2023

One of the important areas research in energy sector is study prospects for using new types nuclear fuel, including tritium, which one most promising fuel thermonuclear energy. At same time, production tritium required quantities, that optimal use blanket materials based on lithium-containing ceramics. This where released from lithium under influence neutron irradiation. The paper presents results an investigation two-phase ceramics Li4SiO4–Li2TiO3 compounds resistance to external influences (mechanical loads) during accumulation hydrogen and helium (He2+) near-surface layer. interest such studies primarily related search solutions field creating high-strength generation its further as fusion, well mechanisms different phases changes strength properties ceramics, provides opportunity expand fundamental knowledge this area. proposed method obtaining by mechanical-chemical mixing subsequent sintering into spherical particles enables well-structured, specified geometric dimensions (limited only mold) with a controlled phase ratio. During experiments, it was found increasing content Li4SiO4 leads increase characteristics (hardness, cracking) 15–20% compared single-phase composition high destructive embrittlement ratio 0.75Li4SiO4–0.25Li2TiO3. factors explaining high-dose irradiation increased dislocation density presence interphase or intergranular boundaries, concentration creation additional obstacles agglomeration

Язык: Английский

Процитировано

1

Microstructure evolution and deuterium permeation behavior of CLF-1 steel under Li4SiO4 tritium breeder corrosion cycles DOI

Hongzhihao,

Wanglong,

Fantao Meng

и другие.

Corrosion Science, Год журнала: 2024, Номер unknown, С. 112658 - 112658

Опубликована: Дек. 1, 2024

Язык: Английский

Процитировано

0