Han En

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Publication

Featured researches published by Han En.

Acta Metallurgica Sinica | 2011

RESEARCH TRENDS ON MICRO AND NANO-SCALE MATERIALS DEGRADATION IN NUCLEAR POWER PLANT

Han En

Journal of the Chinese Society of Corrosion and Protection | 2011

STRESS CORROSION CRACKING BEHAVIOR OF X100 PIPELINE STEEL IN NS4 SOLUTION UNDER CONSTANT LOADING TEST

Han En

Journal of the Chinese Society of Corrosion and Protection | 2012

INFLUENCE OF DISSOLVED HYDROGEN ON OXIDATION OF STAINLESS STEEL 316L IN SIMULATED PWR PRIMARY WATER

Han En

Acta Metallurgica Sinica | 2012

CORROSION BEHAVIOR OF NUCLEAR GRADE ALLOYS 690 AND 800 IN SIMULATED HIGH TEMPERATURE AND HIGH PRESSURE PRIMARY WATER OF PRESSURIZED WATER REACTOR

Han En

Acta Metallurgica Sinica | 2011

ANALYSES OF SURFACE OXIDE FILMS ON ELECTROPOLISHED ALLOY 690TT AFTER IMMERSION FOR DIFFERENT TIMES

Han En

Journal of the Chinese Society of Corrosion and Protection | 2008

PRESENT STATUS AND DEVELOPMENT ON ELECTROCHEMISTRY AT HIGH TEMPERATURES AND HIGH PRESSURES AQUEOUS SYSTEMS

Han En

Journal of the Chinese Society of Corrosion and Protection | 2008

EFFECT OF MECHANICAL FACTORS ON SCC INITIATION OF PIPELINE STEEL

Han En

Journal of the Chinese Society of Corrosion and Protection | 2013

Influence of Cr Addition on Corrosion Behavior of Cast X52 Steel in Wet H_2S Environment at 30

Han En

Journal of the Chinese Society of Corrosion and Protection | 2012

ELECTROCHEMICAL NOISE ANALYSIS OF 304 STAINLESS STEEL PITTING CORROSION IN FERRIC CHLORIDE SOLUTION

Han En

Journal of the Chinese Society of Corrosion and Protection | 2012

REVIEW ON RELATIONSHIP BETWEEN DYNAMIC STRAIN AGING AND ENVIRONMENTALLY ASSISTED CRACKING OF STRUCTURAL MATERIALS USED IN NUCLEAR POWER PLANTS

Han En

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Chinese Academy of Sciences

Archive Network Publication Hotspot Collaboration

Network

Latest external collaboration on country level. Dive into details by clicking on the dots.

Hotspot

Dive into the research topics where Han En is active.

Publication

Featured researches published by Han En.

RESEARCH TRENDS ON MICRO AND NANO-SCALE MATERIALS DEGRADATION IN NUCLEAR POWER PLANT

STRESS CORROSION CRACKING BEHAVIOR OF X100 PIPELINE STEEL IN NS4 SOLUTION UNDER CONSTANT LOADING TEST

INFLUENCE OF DISSOLVED HYDROGEN ON OXIDATION OF STAINLESS STEEL 316L IN SIMULATED PWR PRIMARY WATER

CORROSION BEHAVIOR OF NUCLEAR GRADE ALLOYS 690 AND 800 IN SIMULATED HIGH TEMPERATURE AND HIGH PRESSURE PRIMARY WATER OF PRESSURIZED WATER REACTOR

ANALYSES OF SURFACE OXIDE FILMS ON ELECTROPOLISHED ALLOY 690TT AFTER IMMERSION FOR DIFFERENT TIMES

PRESENT STATUS AND DEVELOPMENT ON ELECTROCHEMISTRY AT HIGH TEMPERATURES AND HIGH PRESSURES AQUEOUS SYSTEMS

EFFECT OF MECHANICAL FACTORS ON SCC INITIATION OF PIPELINE STEEL

Influence of Cr Addition on Corrosion Behavior of Cast X52 Steel in Wet H_2S Environment at 30

ELECTROCHEMICAL NOISE ANALYSIS OF 304 STAINLESS STEEL PITTING CORROSION IN FERRIC CHLORIDE SOLUTION

REVIEW ON RELATIONSHIP BETWEEN DYNAMIC STRAIN AGING AND ENVIRONMENTALLY ASSISTED CRACKING OF STRUCTURAL MATERIALS USED IN NUCLEAR POWER PLANTS

Collaboration

Dive into the Han En's collaboration.