Luca Capriotti

idaho national laboratory

H指数:17

被引数:868

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TEM characterization of two variants of fuel-cladding chemical interaction in a HT-9 Clad U-10Zr fuel. Variant 2: FCCI without a Zr rind

透射电子显微镜对HT-9包壳U-10Zr燃料中两种燃料-包壳化学相互作用变体的表征。变体2：无Zr外壳的FCCI

Journal of Nuclear Materials

IF3.2

2026-08-120

OAAI

Plutonium migration and phase evolution in irradiated U-Pu-Zr metallic fuels: An integrated EPMA-SEM-TEM study

钚迁移和相演变在辐照U-Pu-Zr金属燃料中的研究：一种集成的EPMA-SEM-TEM方法

Journal of Nuclear Materials

IF3.2

2026-04-120

PRE

FIB-ToF-SIMS characterization of irradiated U-10Zr

FIB-ToF-SIMS表征辐照后的U-10Zr

Materials Characterization

IF5.5

2026-03-230

PRE

Modern Measurement of Local Radial Thermal Conductivity of Irradiated He-Bonded U-10 wt. % Zr Annular Fuel: A cross-correlative study with electron probe microanalysis techniques

Journal of Nuclear Materials

IF3.2

2026-01-280

PRE

3D pore structure reconstruction of fluff region in top of EBR-II irradiated fuel by X-ray micro-computed tomography

EBR-II辐照燃料顶部绒毛区域3D孔结构重建的X射线显微计算机断层扫描

Journal of Nuclear Materials

IF3.2

2025-09-200

PRE

Nanoscale clustering and fission product segregation in irradiated annular U-10Zr fuel

辐照环形U-10Zr燃料中的纳米尺度团簇和裂变产物偏聚

Journal of Nuclear Materials

IF3.2

2025-09-050

PRE

Elucidating the effect of minor-actinide addition on fuel-cladding chemical interaction in an HT-9 clad U-Pu-Zr metallic fuel irradiated to 6.15 at.% burnup in EBR-II

阐明在EBR-II中辐照至6.15 at.%燃耗的HT-9包壳U-Pu-Zr金属燃料中，添加次锕系元素对燃料-包壳化学相互作用的影响

Journal of Nuclear Materials

IF3.2

2025-08-070

PRE

An integrated approach to examine fuel-cladding chemical interaction in HT9/U-10Zr metallic fast reactor fuels: Coupling machine learning with electron microscopy and local mechanical properties analysis

一种综合方法用于研究HT9/U-10Zr金属快堆燃料中的燃料-包壳化学相互作用：结合机器学习与电子显微镜及局部力学性能分析

Journal of Nuclear Materials

IF3.2

2025-08-060

PRE

High resolution microstructural, chemical studies and localized burnup analysis in an irradiated U10Zr metallic fuel

高分辨率微观结构、化学研究以及在辐照U10Zr金属燃料中的局部燃耗分析

Materials Characterization

IF5.5

2025-08-050

PRE

Comparative post-irradiation examination of high burnup U-19Pu-10Zr: Assessing steady-state irradiation behavior against historical and modeled fuel performance

高燃耗U-19Pu-10Zr的对比辐照后检验：评估稳态辐照行为与历史及模型化燃料性能

JOURNAL OF NUCLEAR MATERIALS

IF3.2

2025-05-010

PRE

Transmission Electron Microscopy Characterization of Fuel Cladding Chemical Interaction between Minor Actinides bearing U-Pu-Zr Fuel and AIM1 Cladding

透射电子显微镜表征含少量锕系元素U-Pu-Zr燃料与AIM1包壳之间的化学相互作用

JOURNAL OF NUCLEAR MATERIALS

IF3.2

2025-03-010

PRE

Fission accelerated steady-state post irradiation examinations - Part II (vol 56, pg 4158, 2024)

裂变加速稳态辐照后检验 - 第II部分（卷56，页4158，2024）

NUCLEAR ENGINEERING AND TECHNOLOGY

IF2.6

2025-02-010

OAAI

Characterization of Fuel Cladding Chemical Interaction on a High Burnup U-10Zr Metallic Fuel via Electron Energy Loss Spectroscopy Enhanced by Machine Learning

MATERIALS CHARACTERIZATION

IF5.5

2024-12-010

PRE

Segmentation and Classification of Fission as Pores in Reactor Iirradiated Annular U-10Zr Metallic Fuel Using Machine Learning Models

MATERIALS CHARACTERIZATION

IF5.5

2024-09-010

PRE

An efficient instance segmentation approach for studying fission gas bubbles in irradiated metallic nuclear fuel

SCIENTIFIC REPORTS

IF3.9

2023-12-141

OAAI

A fine pore-preserved deep neural network for porosity analytics of a high burnup U-10Zr metallic fuel

SCIENTIFIC REPORTS

IF3.9

2023-12-142

OAAI

Advanced characterization-informed machine learning framework and quantitative insight to irradiated annular U-10Zr metallic fuels

SCIENTIFIC REPORTS

IF3.9

2023-06-305

OAAI

TEM-based phase characterization of U-19Pu-10Zr irradiated in ATR

MRS BULLETIN

IF4.9

2022-11-021

PRE

Understanding fission gas bubble distribution, lanthanide transportation, and thermal conductivity degradation in neutron-irradiated α-U using machine learning

MATERIALS CHARACTERIZATION

IF5.5

2022-02-0111

OAAI

Characterization of metallic fuel for minor actinides transmutation in fast reactor

PROGRESS IN NUCLEAR ENERGY

IF3.2

2017-01-0125

OAAI

Luca Capriotti

个人简介

教育背景

工作经历

荣誉奖项

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