Dahuan Zhu

Hefei Institutes of Physical Science

H指数:17

被引数:866

个人简介

暂无内容

教育背景

暂无内容

工作经历

暂无内容

荣誉奖项

暂无内容

Fast diffusion of hydrogen isotopes at low temperatures and the influence of isotope effects on exchange behavior

低温下氢同位素的快速扩散及同位素效应对交换行为的影响

Journal of Nuclear Materials

IF3.2

2026-07-010

PRE

Forced convection heat transfer and thermal stratification of helium-xenon mixtures along close-packed rod arrays

氦-氙混合物沿密排棒阵列的强制对流换热与热分层现象

International Journal of Heat and Mass Transfer

IF5.8

2026-03-140

PRE

First results of LHW-generated fast electron-induced melting of TZM limiter in EAST

Nuclear Fusion

IF4

2026-01-290

Research on Accident Diagnosis Model Driven by a Hybrid of Knowledge and Data

知识数据融合驱动的故障诊断模型研究

PROCEEDINGS OF THE 32ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING-VOL 7; ICONE 2025

IF0

2026-01-010

PRE

Evolution and impacts of ITER-like W/Cu monoblocks with interface damage in EAST

ITER类似W/Cu单块在界面损伤下的演化与影响研究

Nuclear Fusion

IF4

2025-12-080

Damage evolution and its impact of the W/Cu flat-type component for divertor target in EAST

EAST偏流板靶板上W/Cu平板型组件的损伤演化及其影响

Nuclear Fusion

IF4

2025-12-020

Synergistic effects of He, Fe, and deuterium ions on tungsten

氦、铁和氘离子对钨的协同效应

INTERNATIONAL JOURNAL OF MECHANICAL SCIENCES

IF9.4

2025-07-010

PRE

Mechanism analysis of microstructural evolution induced by Y2O3 particles during the rolling process of W-Y2O3 composite

Y₂O₃颗粒在W-Y₂O₃复合材料轧制过程中诱导微观结构演化的机制分析

international journal of refractory metals hard materials

IF0

2025-06-130

PRE

Enhanced thermal stability and irradiation resistance of ODS-W/CuCrZr joints by interlayer employ and interface improvement

通过中间层应用和界面改进提高ODS-W/CuCrZr接头的热稳定性和抗辐照性

JOURNAL OF NUCLEAR MATERIALS

IF3.2

2025-06-010

PRE

Microstructure evolution and hardening of helium ion irradiated tungsten

VACUUM

IF3.9

2025-05-010

PRE

Characterization of in situ damage to tungsten PFCs induced by transient heat flux during plasma disruption in EAST

NUCLEAR FUSION

IF4

2025-04-010

Experimental and numerical investigation on the circumferential non-uniform heat transfer characteristics in a wire-wrapped tight lattice bundle

INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER

IF6.4

2025-03-010

PRE

Effects of repetitive thermal loads on microstructure and mechanical properties of potassium-doped tungsten alloy as plasma facing material

NUCLEAR FUSION

IF4

2025-01-310

Modelling study of divertor W leakage for different divertor conditions with Ne seeding in EAST tokamak

NUCLEAR FUSION

IF4

2024-10-150

Melting of W/Cu flat type component for main limiter and its impact on plasma operation in EAST experiments

NUCLEAR FUSION

IF4

2024-06-281

Long-term plasma exposure of ITER-like W/Cu monoblocks with pre-damaged surfaces in EAST experiments

NUCLEAR FUSION

IF4

2024-06-032

Drifts effect on the divertor W leakage mechanisms under different dissipative divertor conditions of EAST

NUCLEAR FUSION

IF4

2024-02-237

Deuterium erosion and retention properties on MoAlB ceramics by ion irradiation

VACUUM

IF3.9

2023-01-013

PRE

Modelling of tungsten impurity edge transport and screening for different divertor conditions in EAST

EAST不同偏滤器条件下钨杂质边缘迁移和筛选的模拟

NUCLEAR FUSION

IF4

2022-10-1013

PRE

In situ leading-edge-induced damages of melting and cracking W/Cu monoblocks as divertor target during long-term operations in EAST

NUCLEAR FUSION

IF4

2022-03-1518

PRE

Dahuan Zhu

个人简介

教育背景

工作经历

荣誉奖项

研究方向