Application of Coating Technology on the Zirconium-Based Alloy to Decrease High-Temperature Oxidation

Similar documents
2017 Water Reactor Fuel Performance Meeting September 10 (Sun) ~ 14 (Thu), 2017 Ramada Plaza Jeju Jeju Island, Korea

2017 Water Reactor Fuel Performance Meeting September 10 (Sun) ~ 14 (Thu), 2017 Ramada Plaza Jeju Jeju Island, Korea

2017 Water Reactor Fuel Performance Meeting September 10 (Sun) ~ 14 (Thu), 2017 Ramada Plaza Jeju Jeju Island, Korea

RESEARCH AND DEVELOPMENT OF COATINGS FOR ZIRCONIUM FUEL CLADDINGS

IRRADIATION TEST RESULTS OF HANA CLADDING IN HALDEN TEST REACTOR AFTER 67 GWD/MTU

Interfaces: Corrosion in Pb-alloy cooled nuclear reactors and advanced mitigation measures

2017 Water Reactor Fuel Performance Meeting September 10 (Sun) ~ 14 (Thu), 2017 Ramada Plaza Jeju Jeju Island, Korea

"DESIGN ISSUES CONCERNING COMPOSITE MATERIAL FUEL-ELEMENT JACKETS BASED ON SILICIUM CARBIDE WITHIH A MATTER OF SAFETY CONCEPT OF WATER- COOLED

2017 Water Reactor Fuel Performance Meeting September 10 (Sun) ~ 14 (Thu), 2017 Ramada Plaza Jeju Jeju Island, Korea

3D Printing of Components and Coating Applications at Westinghouse

Joining of C f /SiC composites with Niobium alloy

2017 Water Reactor Fuel Performance Meeting September 10 (Sun) ~ 14 (Thu), 2017 Ramada Plaza Jeju Jeju Island, Korea

ON-GOING STUDIES AT CEA ON CHROMIUM COATED ZIRCONIUM BASED NUCLEAR FUEL CLADDINGS FOR ENHANCED ACCIDENT TOLERANT LWRS FUEL

In-pile testing of CrN, TiAlN and AlCrN coatings on Zircaloy cladding in the Halden Reactor

Thermal Conductivity and Sintering Behavior of Hafnia-based Thermal Barrier Coating Using EB-PVD

CONTENTS. Preface to the 3rd Edition Acknowledgments

2017 Water Reactor Fuel Performance Meeting September 10 (Sun) ~ 14 (Thu), 2017 Ramada Plaza Jeju Jeju Island, Korea

Structural materials for Fusion and Generation IV Fission Reactors

CHARACTERIZATION OF OXYGEN DISTRIBUTION IN LOCA SITUATIONS

Overview of ATF research and ongoing experiments at the Halden reactor project

Advanced Zirconium Alloy for PWR Application

Topic 1: Fuel Fabrication. Daniel Mathers and Richard Stainsby

Silver Diffusion Bonding and Layer Transfer of Lithium Niobate to Silicon

Microstructure and Vacuum Leak Characteristics of SiC coating Layer by Three Different Deposition Methods

Registration. Break. Kyoto U. Oral #10 R. KASADA Tohoku U. Tohoku U. Oral #15 T. NAGASAKA NIFS

4-in-1 Nano Machine & Technology

Materials for elevated temperature heat exchangers in reactors

Westinghouse ACCIDENT TOLERANT FUEL PROGRAM

Enhanced Accident Tolerant Fuel at AREVA NP. Dr. Elmar Schweitzer, Dr. Jeremy Bischoff COP23, Bonn, 11/08/2017

Appendix 1: Development of LWR Fuels with Enhanced Accident Tolerance; Task 1 Technical Concept Description

Mo-9Si-8B alloys with additons of Zr microstructure and creep properties

Evaluations of Mo-alloy for light water reactor fuel cladding to enhance accident tolerance

Oxford University Materials 2005

A High Temperature Gas Loop to Simulate VHTR and Nuclear Hydrogen Production System

Relationship between Microstructure and Vacuum Leak Characteristics of SiC Coating Layer

Nuclear Fission Renaissance: Opportunities for Research

Jānis Grabis. Plasma chemical synthesis of multicomponent nanopowders, their characteristics, and processing

4.2 DEVELOPMENT OF FUEL TEST LOOP IN HANARO

SAFETY ENHANCEMENT TECHNOLOGY DEVELOPMENT WITH COLLABORATIVE INTERNATIONAL ACTIVITY

2017 Water Reactor Fuel Performance Meeting September 10 (Sun) ~ 14 (Thu), 2017 Ramada Plaza Jeju Jeju Island, Korea

Mobile repair of hard coated rolls and machine components. ICE Europe Technical Program, Dr. A. Barth,

Status of NEA Nuclear Science activities related to accident tolerant fuels

2017 Water Reactor Fuel Performance Meeting September 10 (Sun) ~ 14 (Thu), 2017 Ramada Plaza Jeju Jeju Island, Korea

Formation of Fe-base Metal Glass Coating by Gas Tunnel Type Plasma Spraying

Post Quench Ductility of Zirconium Alloy Cladding Materials

Influence of Spraying Conditions on Properties of Zr-Based Metallic Glass Coating by Gas Tunnel Type Plasma Spraying

Physical Properties. Can increase the strength by cold working but the recrystallization temperature is 400 to 500 C

Oxidation, Environmental Coatings and Phase Stability in Mo-Si-B Alloys and Diboride Systems

TECHNOLOGY OF CREATION COATINGS BASED ON FeCrAlY.

Advanced LWR Fuels Research in the United States Shannon Bragg-Sitton Idaho National Laboratory

Aluminum Alloys GOTChA Chart

R&D activities related to nuclear fuel performance and technology at the DG JRC. Paul VAN UFFELEN

STRENGTH OF STEELS EXPOSED TO HEAVY LIQUID METALS

Engineered Zircaloy Cladding Modifications for Improved Accident Tolerance of LWR Fuel

ATI 332 ATI 332. Technical Data Sheet. Stainless Steel: Austenitic GENERAL PROPERTIES TYPICAL ANALYSIS PHYSICAL PROPERTIES

Chemical reactivity of oxide materials with uranium and uranium trichloride

Involvement of EDF in the Halden Reactor Project: a long-term cooperation in R&D

Development of New Generation Of Coatings with Strength-Ductility Relationship, Wear, Corrosion and Hydrogen Embrittlement Resistance Beyond the

Thermal Expansion of Al Matrix Composites Reinforced with TiN Nanoparticles

Nickel-free Metal Finishes

Properties of Fe-base Metal Glass Coatings Produced by Gas Tunnel Type Plasma Spraying

2017 Water Reactor Fuel Performance Meeting September 10 (Sun) ~ 14 (Thu), 2017 Ramada Plaza Jeju Jeju Island, Korea

Wear Resistance of AlN-Al Cermet Coatings Deposited by HVOF Spray Process. Matsumoto, Taihei; Cui, Lin; Nogi, Kiyoshi

Surface Modification of AISI 1020 Steel with TiC Coating by TIG Cladding Process

THE STRUCTURE AND MECHANICAL PROPERTIES OF NiCrBSi COATINGS PREPARED BY LASER BEAM CLADDING

A Novel Thermal Management Approach for Packaging of High Power GaN Devices

THE QUEST FOR SAFE AND RELIABLE FUEL CLADDING MATERIALS

Thermal Durability and Abradability of Plasma Sprayed Al-Si-Polyimide Seal Coatings p. 85

All fabrication was performed on Si wafers with 285 nm of thermally grown oxide to

Class Alloy Alloying Additions (%) Form Condition

20th IAEA Fusion Energy Conference 1-6 November 2004 Vilamoura, Portugal. Recent Results in Plasma Facing Materials Studied at SWIP

Cutting Tool Materials and Cutting Fluids. Dr. Mohammad Abuhaiba

Surface composites: A new class of engineered materials

2017 Water Reactor Fuel Performance Meeting September 10 (Sun) ~ 14 (Thu), 2017 Ramada Plaza Jeju Jeju Island, Korea

Laser Cladding Services

Physical Vapor Deposition (PVD) Zheng Yang

PROPERTIES OF THE SIBOR OXIDATION PROTECTIVE COATING ON REFRACTORY METAL ALLOYS

STRUCTURAL STABILITY OF THERMAL BARRIER COATINGS PRODUCED BY THERMAL SPRAYING

2017 Water Reactor Fuel Performance Meeting September 10 (Sun) ~ 14 (Thu), 2017 Ramada Plaza Jeju Jeju Island, Korea

Developing Fuels with Enhanced Accident Tolerance. Fiona Rayment and Dave Goddard

Activities on ODS steels for Gen IV Cladding tubes

Amorphous and Polycrystalline Thin-Film Transistors

Laser damage threshold of AR coatings on phosphate glass

LATTICE STRAIN EFFECT ON GRAIN GROWTH DURING SPARK PLASMA SINTERING OF ZrC AND W-ZRC

Oxidation of Ti 2 AlC in High Temperature Steam Environment

Joint Technology Initiatives Collaborative Project (FCH) FCH-JU WP4 - Development of lab-scale cell components

New sintered materials & processes of joining of nickel super alloys and metal-ceramics using nanostructured interlayers

Laser assisted Cold Spray

Self-Healing Thermal Barrier Coatings. Advanced Materials December 12 th, Presenter: Marcel van Wonderen

General corrosion of iron, nickel and titanium alloys as candidate materials for the fuel claddings of the supercritical-water cooled power reactor

Development of Low Activation Structural Materials

ATI 418 SPL alloy is readily forgeable and has fair machinability and cold formability in the annealed condition.

Feasibility Study of Supercritical Light Water Cooled Fast Reactors for Actinide Burning and Electric Power Production

Past, Present and Future of the Republic Center for Structure Researches of Georgian Technical University

PHYS 534 (Fall 2008) Process Integration OUTLINE. Examples of PROCESS FLOW SEQUENCES. >Surface-Micromachined Beam

Global Journal of Engineering Science and Research Management

Laser Machining Processes Laser heat processing divided into 3 regions Heating Melting Vaporization

Materials in Generation-IV Very High Temperature Reactors Challenges and Opportunities

Cold Spray Coatings for Prevention and Mitigation of Stress Corrosion Cracking

Fabrication Process. Crystal Growth Doping Deposition Patterning Lithography Oxidation Ion Implementation CONCORDIA VLSI DESIGN LAB

Transcription:

Application of Coating Technology on the Zirconium-Based Alloy to Decrease High-Temperature Oxidation Hyun-Gil Kim*, Il-Hyun Kim, Jeong-Yong Park, Yang-Hyun Koo, KAERI, 989-111 Daedeok-daero, Yuseong-gu, Daejeon, 305-353, Republic of Korea *Corresponding author: hgkim@kaeri.re.kr

Accident-tolerant fuel claddings (ATFC) The breakthrough to the challenge facing nuclear fuels of LWR after Fukushima Dai-ichi accident involves the development of accident-tolerant fuels. Fukushima accident New requirements have been emerged on the performance of fuel to provide a more extended safety margin. One of the research efforts to enhance the accident-tolerance of nuclear fuels relies on the improvement in the oxidation resistance of claddings with the reduction of hydrogen emission. Hydrogen explosion Zr + 2H 2 O ZrO 2 + 2H 2 2

Technical issue Technical issues to development of ATFC Normal operation condition - High burn-up (higher corrosion/creep resistance) - Load follow (higher strength/fatigue resistance) Zr-based alloys Accident condition - High temperature oxidation (lower oxidation rate) - High temperature ballooning (higher creep/deformation resistance) Surface modified Zr alloys - Zr alloy + surface alloying, coating Hybrid materials - Zr alloy + thermo-stable materials (SiC, Nb, Mo ) Full ceramic materials - SiC/SiC f composite - Others (?) Increasing challenges - Fabrication - Economy - Verification Time to development 3

Challenges to ATFC Application of new materials raises many issues on the performance and the integrity of the claddings. - Oxidation resistance - Adhesion to the matrix - Phase stability up to high temp. - Thermal expansion coefficient - Neutron economy - Thermal conductivity - Irradiation susceptibility - Tube fabricability - Unknowns Zr alloys Surface modification 4

Cladding Y 2 O 3, SiC, Cr 3 C 2, N, C, Si, Cr Cladding Y 2 O 3, SiC, Cr 3 C 2, N, C, Si, Cr Cladding Y 2 O 3, SiC, Cr 3 C 2, N, C, Si, Cr Y 2 O 3, SiC, Cr 3 C 2, N, C, Si, Cr Concept of surface modification technology 1. Coating of corrosion resistance material on cladding 2. Mixing of coated material into cladding 3. Additional coating of corrosion resistance material Coating method develop. Vacuum evaporation Plasma spray Laser beam scanning (with coated powder) Combine of coating methods Mixing method develop. Laser beam scanning Ion implantation Annealing Additional coating method develop. Vacuum evaporation Plasma spray Laser beam scanning with coated powder Annealing Performance evaluation Corrosion test : up to 1200 o C (normal operation and LOCA-simulated conditions) Adhesion test : thermal cycle (thermal expansion), mechanical deformation and impact Micro-structural analysis 5

Oxide Carbide Materials Phase Transform. Temp. ( o C) Melting Point ( o C) Thermal Expansion Coff. (x 10-6 K) Thermal Conductivity (W/mK) Y 2 O 3 none 2690 8.1 1.0 SiO 2 Depend on pressure 1600 12.3 1.3 Cr 2 O 3 none 2400 9.0 2-5(coating) Al 2 O 3 none 2072 8.4 5-25(bulk) ZrO 2 M(970)/ T(1205)/Cubic 2130 10.1 1.8-3.0 Cr 3 C 2 none 1895 10.3 13 SiC(CVD) none 2545 <5 330 ZrC none 3540 7.01 12 Nitride ZrN none 1960 7.24 10 Metal Consideration of coating materials Neutron Cross Section (barn) 1.28(Y) 0.0002(O) 0.177(Si) 0.0002(O) 3.05(Cr) 0.0002(O) 0.231(Al) 0.0002(O) 0.182(Zr) 0.0002(O) 3.05(Cr) 0.0035(C) 0.177(Si) 0.0035(C) 0.185(Zr) 0.0035(Cr) 0.185(Zr) 1.9(N) Cr none 1907 4.9 93.9 3.05(Cr) Si none 1414 2.6 149 0.177(Si) Substrate Zr HCP(863)/BCC 1850 7.2 10 0.185(Zr) 6

Phase diagram of coating material and Zr Zr-Si Zr-Cr 7

Consideration of coating technologies Plasma spray method Laser beam scanning method Plasma spray Laser beam scanning 8

High temperature oxidation test Temperature was increased at 50 o C/min to 1200 o C, maintained at 1200 o C for 2000s and then Ar gas-cooled. Steam was supplied right after the temperature reached 1200 o C. 9

Weight Gain, mg/dm 2 Oxidation behavior of selected coating materials 10000 1000 100 Metal Cr Si wafer SiO 2 10 1 0 500 1000 1500 2000 2500 Time, s 10

Analysis of Si-coated layer by PS 1pass 3pass 6pass Si-layer 100 m 100 m 100 m 11

Comparison of Si-coated layer by PS and PS+LBS PS PS+LBS Si layer Epoxy Si-Zr mixed layer 50 m 12

Analysis of Si-coated layer by PS+LBS Si-Zr mixed layer Si and mixed grain (5~20 at% Si; 80~95 at% Zr) 50 m Coated surface direction grain (~99 at% Zr) 13

Oxidation behavior of Si-coated samples 10000 Weight Gain, mg/dm 2 1000 100 10 Si-coated by PS Si-coated by PS + LBS 1 0 500 1000 1500 2000 2500 Time, s 14

Si-coated layer by PS after oxidation 1pass 3pass 6pass Si-layer ZrO 2 Si-layer ZrO 2 Si-layer ZrO 2 200 m 200 m 200 m 200 m 15

Comparison of oxidation resigons Zr PS PS+LBS ZrO 2 Si-layer -Zr(O) ZrO 2 Si-Zr mixed layer 200 m 200 m 200 m 16

Comparison of oxidation characteristics PS PS+LBS After oxidation Si-layer spalled region Epoxy ZrO 2 Si-Zr mixed layer Before oxidation PS PS+LBS Si layer Epoxy Si-Zr mixed layer 50 m 50 m 17

Analysis of Si-Zr mixed layer after oxidation Oxidized Si-Zr mixed layer Pt Oxidized Si-Zr mixed layer Large grain region O: 30~40 at% Si: 5~20 at% Zr: 40~65 at% ZrO 2 -Zr(O) 200 m 200 m Slim grain region O: 20~30 at% Si: 5~20 at% Zr: 50~75 at% FIB damage 18

Future plan Verification of coating materials (Si and Cr) Simplified of coating method (Powder supplied LBS) 1) Control of the coated thickness, composition, and phase Manufacture of tube samples Performance test of surface coated tube samples - Very high temperature oxidation test higher than 1200 o C - Strength and creep ballooning test at high temperature - Basic physical performance test - Others 1) Zr alloys Surface modification 19

Summary Coating techniques both the coating methods and coating materials to reduce the oxidation rate of zirconium-based alloy in a high-temperature steam environment were studied. After 1200 o C test in steam environment, the SiO 2 showed the highest oxidation resistance among the tested materials, and Si was more effective than Cr from the viewpoint of oxidation resistance. Plasma spray (PS) and laser beam scanning (LBS) after a PS were selected as the coating method, and the Si was chosen as a coating layer for the surface coating material on zirconiumbased alloy. PS coating technique has problems such as the formation of pores in the Si-coated layer and the interface oxidation caused by low adhesion property. By the LBS treatment, the pores in the Si-coated layer by PS were successively removed, and the interface oxidation was suppressed by the formation of the diffusion bonding between substrate and Si-Zr mixed layer. Oxidation resistance of the Si-Zr mixed layer is superior to that of, and a good adhesion property can be obtained. Thus, the hydrogen generation of zirconium alloy by an excess oxidation reaction in a high-temperature steam environment can be considerably reduced by the application of the Si coating technology of PS + LBS treatments. 20

Thanks for your attention!