1
|
Aspects of Applied Chemistry Related to Future Goals of Safety and Efficiency in Materials Development for Nuclear Energy. MOLECULES (BASEL, SWITZERLAND) 2023; 28:molecules28020874. [PMID: 36677931 PMCID: PMC9866518 DOI: 10.3390/molecules28020874] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Figures] [Subscribe] [Scholar Register] [Received: 11/14/2022] [Revised: 01/10/2023] [Accepted: 01/13/2023] [Indexed: 01/18/2023]
Abstract
The present paper is a narrative review focused on a few important aspects and moments of trends surrounding materials and methods in sustainable nuclear energy, as an expression of applied chemistry support for more efficiency and safety. In such context, the paper is focused firstly on increasing alloy performance by modifying compositions, and elaborating and testing novel coatings on Zr alloys and stainless steel. For future generation reactor systems, the paper proposes high entropy alloys presenting their composition selection and irradiation damage. Nowadays, when great uncertainties and complex social, environmental, and political factors influence energy type selection, any challenge in this field is based on the concept of increased security and materials performance leading to more investigations into applied science.
Collapse
|
2
|
Zhang H, Cheng J, Lian P, He Z, Wang Q, Yu A, Song J, Tang Z, Liu Z. Effects of irradiation on nano-pore phenol-formaldehyde resin infiltrated IG-110 graphite. NUCLEAR MATERIALS AND ENERGY 2022. [DOI: 10.1016/j.nme.2022.101215] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/17/2022]
|
3
|
Zhao R, Jia H, Cao S, Tong Z, Zhou Z. Effect of the addition of Y and Y2O3 on microstructure and mechanical properties of 15Cr-15Ni ODS steel. NUCLEAR MATERIALS AND ENERGY 2022. [DOI: 10.1016/j.nme.2022.101196] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
|
4
|
Yu D, Tan Y. Evolution of the oxidation behaviors of highly oxidation-resistant (Ti 0.8Nb 0.2)C in 1000–1200 °C steam. RSC Adv 2022; 12:20492-20498. [DOI: 10.1039/d2ra02337g] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 04/11/2022] [Accepted: 06/27/2022] [Indexed: 11/21/2022] Open
Abstract
The evolution of the oxidation behaviors of (Ti0.8Nb0.2)C reveals that the outward diffusion of the metal elements plays a decisive role during oxidation and the diffusion rate disparity gives rise to diverse oxidation behaviors.
Collapse
Affiliation(s)
- Dan Yu
- School of Physics and Optoelectronic Engineering, Shandong University of Technology, Zibo, 255000, China
| | - Yongqiang Tan
- Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang, 621900, China
| |
Collapse
|
5
|
Liquid lead flow-accelerated corrosion testing with the rotating cage set-up: A CFD optimisation. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2021.108620] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
|
6
|
Neutron and gamma radiation shielding Ni based new type super alloys development and production by Monte Carlo Simulation technique. Radiat Phys Chem Oxf Engl 1993 2021. [DOI: 10.1016/j.radphyschem.2021.109630] [Citation(s) in RCA: 16] [Impact Index Per Article: 5.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
|
7
|
Suthar F, Shah H, Chaudhury S. A review on application of nickel base hardfacing alloys in sodium-cooled fast reactor. RECENT TRENDS IN MANUFACTURING TECHNOLOGIES, MATERIALS PROCESSING, AND TESTING 2021. [DOI: 10.1063/5.0068164] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 07/19/2023]
|
8
|
Guo S, Xu D, Liang Y, Li Y, Yang J, Chen G, Macdonald DD. Corrosion Characteristics of Typical Ni–Cr Alloys and Ni–Cr–Mo Alloys in Supercritical Water: A Review. Ind Eng Chem Res 2020. [DOI: 10.1021/acs.iecr.0c04292] [Citation(s) in RCA: 13] [Impact Index Per Article: 3.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
Affiliation(s)
- Shuwei Guo
- Key Laboratory of Thermo-Fluid Science & Engineering, Ministry of Education, School of Energy and Power Engineering, Xi’an Jiaotong University, Xi’an, Shaanxi Province 710049, China
| | - Donghai Xu
- Key Laboratory of Thermo-Fluid Science & Engineering, Ministry of Education, School of Energy and Power Engineering, Xi’an Jiaotong University, Xi’an, Shaanxi Province 710049, China
| | - Yu Liang
- Key Laboratory of Thermo-Fluid Science & Engineering, Ministry of Education, School of Energy and Power Engineering, Xi’an Jiaotong University, Xi’an, Shaanxi Province 710049, China
| | - Yanhui Li
- Key Laboratory of Thermo-Fluid Science & Engineering, Ministry of Education, School of Energy and Power Engineering, Xi’an Jiaotong University, Xi’an, Shaanxi Province 710049, China
- Departments of Nuclear Engineering & Materials Science and Engineering, University of California at Berkeley, Berkeley, California 94720, United States
| | - Jianqiao Yang
- Key Laboratory of Thermo-Fluid Science & Engineering, Ministry of Education, School of Energy and Power Engineering, Xi’an Jiaotong University, Xi’an, Shaanxi Province 710049, China
| | - Gang Chen
- Shaanxi Coal and Chemical Technology Institute Co., Ltd., Xi’an, Shaanxi Province 710070, China
| | - Digby D. Macdonald
- Departments of Nuclear Engineering & Materials Science and Engineering, University of California at Berkeley, Berkeley, California 94720, United States
| |
Collapse
|
9
|
Windes W, Burchell T, Davenport M. The advanced reactor technologies (art) graphite R&D program. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110586] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
|
10
|
The effects induced by proton irradiation on structural characteristics of nuclear graphite. J Radioanal Nucl Chem 2019. [DOI: 10.1007/s10967-019-06615-5] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
|
11
|
Schroer C, Tsisar V, Durand A, Wedemeyer O, Skrypnik A, Konys J. Corrosion in Iron and Steel T91 Caused by Flowing Lead–Bismuth Eutectic at 400 °C and 10−7 Mass% Dissolved Oxygen. JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE 2019. [DOI: 10.1115/1.4040937] [Citation(s) in RCA: 10] [Impact Index Per Article: 2.0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/08/2022]
Abstract
Specimens produced from technically pure iron and two different heats of ferritic/martensitic steel T91 are investigated after exposure to oxygen-containing flowing lead–bismuth eutectic (LBE) at 400 °C, 10−7 mass% dissolved oxygen, and flow velocity of 2 m/s, for exposure times between around 1000 and 13,000 h. The occurring phenomena are analyzed and quantified using metallographic cross sections prepared after exposure. While pure iron mostly shows solution underneath or in the absence of a detached and buckled oxide scale, solution in T91 occurs only in a few spots on the sample surface. However, in the case of one of the investigated heats, a singular event of exceptionally severe solution-based corrosion is observed. The results are compared especially with findings at 450 and 550 °C and otherwise similar conditions as well as austenitic steels tested in the identical experimental run.
Collapse
Affiliation(s)
- Carsten Schroer
- Karlsruher Institut für Technologie (KIT), Institut für Angewandte Materialien— Angewandte Werkstoffphysik (IAM-AWP), Hermann-von-Helmholtz-Platz 1, Eggenstein-Leopoldshafen 76344, Germany e-mail:
| | - Valentyn Tsisar
- Karlsruher Institut für Technologie (KIT), Institut für Angewandte Materialien— Angewandte Werkstoffphysik (IAM-AWP), Hermann-von-Helmholtz-Platz 1, Eggenstein-Leopoldshafen 76344, Germany
| | - Adeline Durand
- Karlsruher Institut für Technologie (KIT), Institut für Angewandte Materialien— Angewandte Werkstoffphysik (IAM-AWP), Hermann-von-Helmholtz-Platz 1, Eggenstein-Leopoldshafen 76344, Germany
| | - Olaf Wedemeyer
- Karlsruher Institut für Technologie (KIT), Institut für Angewandte Materialien— Angewandte Werkstoffphysik (IAM-AWP), Hermann-von-Helmholtz-Platz 1, Eggenstein-Leopoldshafen 76344, Germany
| | - Aleksandr Skrypnik
- Karlsruher Institut für Technologie (KIT), Institut für Angewandte Materialien— Angewandte Werkstoffphysik (IAM-AWP), Hermann-von-Helmholtz-Platz 1, Eggenstein-Leopoldshafen 76344, Germany
| | - Jürgen Konys
- Karlsruher Institut für Technologie (KIT), Institut für Angewandte Materialien— Angewandte Werkstoffphysik (IAM-AWP), Hermann-von-Helmholtz-Platz 1, Eggenstein-Leopoldshafen 76344, Germany
| |
Collapse
|
12
|
Enhanced diffusion of Cr in 20Cr-25Ni type alloys under proton irradiation at 670 °C. NUCLEAR MATERIALS AND ENERGY 2018. [DOI: 10.1016/j.nme.2018.10.001] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
|
13
|
Micro mechanical testing of candidate structural alloys for Gen-IV nuclear reactors. NUCLEAR MATERIALS AND ENERGY 2018. [DOI: 10.1016/j.nme.2018.05.018] [Citation(s) in RCA: 19] [Impact Index Per Article: 3.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
|
14
|
Carroll MC, Windes WE, Rohrbaugh DT, Strizak JP, Burchell TD. Leveraging comprehensive baseline datasets to quantify property variability in nuclear-grade graphites. NUCLEAR ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.nucengdes.2016.06.028] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
|
15
|
Oxidation behavior of austenitic stainless steels as fuel cladding candidate materials for SCWR in superheated steam. NUCLEAR ENGINEERING AND DESIGN 2014. [DOI: 10.1016/j.nucengdes.2014.08.020] [Citation(s) in RCA: 14] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
|
16
|
Sun C, Bufford D, Chen Y, Kirk MA, Wang YQ, Li M, Wang H, Maloy SA, Zhang X. In situ study of defect migration kinetics in nanoporous Ag with enhanced radiation tolerance. Sci Rep 2014; 4:3737. [PMID: 24435181 PMCID: PMC3894537 DOI: 10.1038/srep03737] [Citation(s) in RCA: 61] [Impact Index Per Article: 6.1] [Reference Citation Analysis] [Abstract] [Track Full Text] [Download PDF] [Figures] [Journal Information] [Subscribe] [Scholar Register] [Received: 07/22/2013] [Accepted: 12/17/2013] [Indexed: 11/17/2022] Open
Abstract
Defect sinks, such as grain boundaries and phase boundaries, have been widely accepted to improve the irradiation resistance of metallic materials. However, free surface, an ideal defect sink, has received little attention in bulk materials as surface-to-volume ratio is typically low. Here by using in situ Kr ion irradiation technique in a transmission electron microscope, we show that nanoporous (NP) Ag has enhanced radiation tolerance. Besides direct evidence of free surface induced frequent removal of various types of defect clusters, we determined, for the first time, the global and instantaneous diffusivity of defect clusters in both coarse-grained (CG) and NP Ag. Opposite to conventional wisdom, both types of diffusivities are lower in NP Ag. Such a surprise is largely related to the reduced interaction energy between isolated defect clusters in NP Ag. Determination of kinetics of defect clusters is essential to understand and model their migration and clustering in irradiated materials.
Collapse
Affiliation(s)
- C. Sun
- Department of Materials Science and Engineering, Texas A&M University, College Station, TX 77843
- Materials Science and Technology Division, Los Alamos National Laboratory, Los Alamos, NM, 87545
| | - D. Bufford
- Department of Materials Science and Engineering, Texas A&M University, College Station, TX 77843
| | - Y. Chen
- Department of Materials Science and Engineering, Texas A&M University, College Station, TX 77843
| | - M. A. Kirk
- Materials Science Division, Argonne National Laboratory, Argonne, IL 60439, USA
| | - Y. Q. Wang
- Materials Science and Technology Division, Los Alamos National Laboratory, Los Alamos, NM, 87545
| | - M. Li
- Nuclear Engineering Division, Argonne National Laboratory, Argonne, IL 60439, USA
| | - H. Wang
- Department of Materials Science and Engineering, Texas A&M University, College Station, TX 77843
- Department of Electrical and Computer Engineering, Texas A&M University, College Station, TX 77843
| | - S. A. Maloy
- Materials Science and Technology Division, Los Alamos National Laboratory, Los Alamos, NM, 87545
| | - X. Zhang
- Department of Materials Science and Engineering, Texas A&M University, College Station, TX 77843
- Department of Mechanical Engineering, Texas A&M University, College Station, TX 77843
| |
Collapse
|
17
|
Karthik C, Kane J, Butt DP, Windes WE, Ubic R. Microstructural characterization of next generation nuclear graphites. MICROSCOPY AND MICROANALYSIS : THE OFFICIAL JOURNAL OF MICROSCOPY SOCIETY OF AMERICA, MICROBEAM ANALYSIS SOCIETY, MICROSCOPICAL SOCIETY OF CANADA 2012; 18:272-278. [PMID: 22264445 DOI: 10.1017/s1431927611012360] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 05/31/2023]
Abstract
This article reports the microstructural characteristics of various petroleum and pitch based nuclear graphites (IG-110, NBG-18, and PCEA) that are of interest to the next generation nuclear plant program. Bright-field transmission electron microscopy imaging was used to identify and understand the different features constituting the microstructure of nuclear graphite such as the filler particles, microcracks, binder phase, rosette-shaped quinoline insoluble (QI) particles, chaotic structures, and turbostratic graphite phase. The dimensions of microcracks were found to vary from a few nanometers to tens of microns. Furthermore, the microcracks were found to be filled with amorphous carbon of unknown origin. The pitch coke based graphite (NBG-18) was found to contain higher concentration of binder phase constituting QI particles as well as chaotic structures. The turbostratic graphite, present in all of the grades, was identified through their elliptical diffraction patterns. The difference in the microstructure has been analyzed in view of their processing conditions.
Collapse
Affiliation(s)
- Chinnathambi Karthik
- Department of Materials Science and Engineering, Boise State University, 1910 University Drive, Boise, ID 83725, USA.
| | | | | | | | | |
Collapse
|
18
|
Chen HP, Kalia RK, Kaxiras E, Lu G, Nakano A, Nomura KI, van Duin ACT, Vashishta P, Yuan Z. Embrittlement of metal by solute segregation-induced amorphization. PHYSICAL REVIEW LETTERS 2010; 104:155502. [PMID: 20481998 DOI: 10.1103/physrevlett.104.155502] [Citation(s) in RCA: 13] [Impact Index Per Article: 0.9] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Received: 11/25/2009] [Indexed: 05/29/2023]
Abstract
Impurities segregated to grain boundaries of a material essentially alter its fracture behavior. A prime example is sulfur segregation-induced embrittlement of nickel, where an observed relation between sulfur-induced amorphization of grain boundaries and embrittlement remains unexplained. Here, 48x10(6)-atom reactive-force-field molecular dynamics simulations provide the missing link. Namely, an order-of-magnitude reduction of grain-boundary shear strength due to amorphization, combined with tensile-strength reduction, allows the crack tip to always find an easy propagation path.
Collapse
Affiliation(s)
- Hsiu-Pin Chen
- Collaboratory for Advanced Computing and Simulations, Department of Physics & Astronomy, University of Southern California, Los Angeles, California 90089-0242, USA
| | | | | | | | | | | | | | | | | |
Collapse
|