Clint A. Sharrad

University of Manchester

H指数:24

被引数:1,872

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

Real-time imaging of cobalt mobility in graphite at elevated temperatures for advanced nuclear applications

高温下石墨中钴迁移的实时成像研究及其在先进核能应用中的意义

Communications Materials

IF9.6

2026-10-260

OAAI

Electrochemical decontamination of nuclear graphite in deep eutectic solvents

核石墨在深共熔溶剂中的电化学去污

Separation and Purification Technology

IF9

2026-08-220

OAAI

Removing oxygen-derived impurities from molten chloride fuel salts with aluminium chloride: Effectiveness and limitations

用氯化铝从熔盐氯化物燃料盐中去除氧系杂质：有效性与局限性

Nuclear Engineering and Technology

IF2.6

2026-08-010

OAAI

Ex-situ and in-situ methods for quantifying moisture concentration in MgCl2-containing molten salts and their impact on materials corrosion

用于量化含MgCl2熔融盐中水分浓度的原位和非原位方法及其对材料腐蚀的影响

Journal of Nuclear Materials

IF3.2

2026-07-011

PRE

SOHIO Process Legacy Waste Treatment: Antimony(V) Removal from Sulfate Media Using Organic Polymeric Ion Exchange Resins

SOHIO工艺遗留废物处理：利用有机聚合物离子交换树脂从硫酸盐介质中去除五价锑

Korean Journal of Chemical Engineering

IF3.2

2026-04-250

OAAI

Structural Recovery and Chemical Characterisation of Ion-Irradiated Graphite for Advanced Nuclear Applications

离子辐照石墨的结构恢复与化学表征及其在先进核能应用中的研究

Carbon

IF11.6

2026-02-080

OAAI

A critical comparison of Pb-loaded organosilica and ion-exchange resins, with bispicolylamine ligands, for adsorption of iodide: Evidence of a ‘matrix effect’ on uptake properties

负载铅的有机硅酸盐和带有双吡啶基胺配体的离子交换树脂对碘离子的吸附：吸附性能中“基质效应”的证据

Chemical Engineering Science

IF4.3

2025-10-170

OAAI

Evolution of irradiated Pile Grade A graphite microstructure under novel molten salt decontamination conditions

辐照堆级A石墨在新型熔盐去污条件下的微观结构演变

Journal of Nuclear Materials

IF3.2

2025-05-300

Development of an automated microfluidic system for actinide separation and analysis

自动化微流体分离分析系统的研制

JOURNAL OF CHROMATOGRAPHY A

IF4

2025-02-010

PRE

Experimental testing and process simulation of flowsheets for the co-separation of uranium and plutonium using acetohydroxamic acid as a complexing agent

PROGRESS IN NUCLEAR ENERGY

IF3.2

2024-11-012

OAAI

Physicochemical properties of extraction solvents for the advanced recycling of spent nuclear fuel

PROGRESS IN NUCLEAR ENERGY

IF3.2

2024-09-013

PRE

Encapsulation of iodine-loaded adsorbents in blended Portland cement and geopolymer wasteforms

负载碘的吸附剂在混合波特兰水泥和地聚合物废物形式中的封装

CEMENT AND CONCRETE RESEARCH

IF13.1

2024-05-010

Benchtop Zone Refinement of Simulated Future Spent Nuclear Fuel Pyroprocessing Waste

模拟未来乏核燃料高温处理废物的台式区域细化

MATERIALS

IF3.2

2024-04-121

OAAI

Development of a Multi-technique Characterization Portfolio for Stainless Steels Exposed to Magnox Reprocessing Liquors

ACS OMEGA

IF4.3

2023-11-171

OAAI

Radioiodine abatement - Development of radioiodine targeting strategies in the light of zero emission

PROGRESS IN NUCLEAR ENERGY

IF3.2

2023-11-013

PRE

Simulation of technetium rejection in an advanced PUREX flowsheet

PROGRESS IN NUCLEAR ENERGY

IF3.2

2023-10-013

OAAI

A review of contamination of metallic surfaces within aqueous nuclear waste streams

PROGRESS IN NUCLEAR ENERGY

IF3.2

2023-05-019

OAAI

Functionality screening to help design effective materials for radioiodine abatement

功能筛选，以帮助设计有效的放射性碘减排材料

FRONTIERS IN CHEMISTRY

IF4.2

2022-10-184

OAAI

A review of technetium and zirconium extraction into tributyl phosphate in the PUREX process

HYDROMETALLURGY

IF5.3

2022-05-0137

OAAI

Combined laser ablation-tuneable diode laser absorption spectroscopy and laser-induced breakdown spectroscopy for rapid isotopic analysis of uranium

激光烧蚀-可调谐二极管激光吸收光谱和激光诱导击穿光谱相结合，用于铀的快速同位素分析

SPECTROCHIMICA ACTA PART B-ATOMIC SPECTROSCOPY

IF3.8

2022-04-0115

PRE

Clint A. Sharrad

个人简介

教育背景

工作经历

荣誉奖项

研究方向