An efficient PDA/Al2O3 nanosheets reinforced ultra-thin ZrO2 coating with attractive anti-corrosion and deuterium resistance property

Z Zheng, H Li, F Li, L Zheng, S Yin, X Wang… - Chemical Engineering …, 2022 - Elsevier
Two-dimensional materials, impermeable to various mediums, have ignited the great
interest in developing multifunction nanocomposite coatings. Even though Al 2 O 3 has …

Effect of surface oxides on tritium entrance and permeation in FeCrAl alloys for nuclear fuel cladding: a review

YS Garud, RB Rebak - Corrosion Reviews, 2023 - degruyter.com
Abstract Iron-chromium-aluminum (FeCrAl) alloys are being considered for the cladding of
uranium dioxide fuel in light water reactors (LWRs). FeCrAl alloys have good mechanical …

Overview of Kyoto Fusioneering's SCYLLA©(“self-cooled yuryo lithium-lead advanced”) blanket for commercial fusion reactors

R Pearson, C Baus, S Konishi, K Mukai… - … on Plasma Science, 2022 - ieeexplore.ieee.org
This article outlines Kyoto Fusioneering's (KF's) initial engineering and development
activities for its self-cooled lithium lead-type blanket: Self-Cooled Yuryo Lithium-Lead …

Status and issues of high-temperature and high-pressure water corrosion research of fusion structural materials in Japanese DEMO reactor development

M Nakajima, T Nozawa - Nuclear Fusion, 2024 - iopscience.iop.org
The activated corrosion product (ACP) assessments of fusion structural materials are
essential to designing components and evaluating workers' radiation exposure. This paper …

Status and initial experiments of DRAGON-V facility for lithium-lead blanket technologies of hydrogen fusion reactors

W Huang, L Sun, Z Jiang, W Ding, Z Xiao… - International Journal of …, 2022 - Elsevier
A dual-coolant integrated experimental facility named DRAGON-V has been developed at
the Institute of Nuclear Energy Safety Technology, Hefei Institute of Physical Science …

Assessment of five concrete types as candidate shielding materials for a compact radiation source based on the IECF

R Ahmed, G Saad Hassan, T Scott, M Bakr - Materials, 2023 - mdpi.com
A radiation source based on the inertial electrostatic confinement fusion (IECF) system is
being developed for multidisciplinary research applications. The radiation outputs from the …

[HTML][HTML] Radiation shielding for inertial electrostatic confinement fusion system utilizing concrete and water

M Bakr, R Ahmed, TW Smith, T Firston… - Journal of Radiation …, 2024 - Elsevier
In this investigation, the impact of water thickness and various types of concrete materials,
each characterized by different densities and elemental compositions, is examined for their …

[HTML][HTML] Fusion neutron source and array of particle detectors for nondestructive interrogation of special nuclear materials

K Masuda, Y Takahashi, T Misawa… - Journal of Applied …, 2024 - pubs.aip.org
Presented herein are the outcomes of an experimental test involving a pioneering portable-
active interrogation system designed for the nondestructive detection of special nuclear …

Effect of Au-ion irradiation on the corrosion behavior of CLF-1 steel

F Bai, W Zhang, L Wang, Y Feng, K Feng, N Liu… - Fusion Engineering and …, 2022 - Elsevier
The corrosion behavior of the CLF-1 steel irradiated by 6 MeV Au-ions with different fluences
was studied by exposing it to a solid tritium breeder (Li 4 SiO 4) in a 0.12 MPa He+ 1% H 2 …

A new direct external recycling concept for the tritium fuel cycle of CFETR

S Cui, S Zheng, Y Lang, J Chen - International Journal of Hydrogen Energy, 2022 - Elsevier
Tritium self-sustaining operation, which is achieved by a successful closed tritium fuel cycle,
is one of the key scientific objectives of China Fusion Engineering Test Reactor (CFETR) …