Michael V. Glazoff

Idaho National Laboratory | INL · Energy and Environment Research Program

The Transient Reactor Test (TREAT) facility that resides in the Materials and Fuels Complex (MFC) at Idaho National Laboratory (INL) first achieved criticality in 1959, and successfully performed many transient tests on nuclear fuel until 1994 when its operations were suspended1. Resumption of operations at TREAT was approved in February 2014 to me...

Embodiments discussed herein in the form of methods, systems, and computer-readable media deal with the application of advanced “projectional” morphological algorithms for solving a broad range of problems. In a method of performing projectional morphological analysis an N-dimensional input is supplied. At least one N-dimensional form indicative of...

Nitrogen is added to stainless steels to improve their toughness and corrosion resistance. However, it is not well understood how nitrogen may impact the precipitate/matrix interfacial properties. In this work, we consider the (FCC) Fe (001)/NbC (001) interface as a model system to study how interfacial structure, energy, and electron charge are af...

We present our results for the concurrent precipitation of metastable M23C6, Nb(C,N) secondary precipitates, and the Nb(C,N) primary crystals in 347H austenitic stainless steel. For precipitation modeling, we have accounted for the elastic contribution to interfacial energy, and for the Fe-spin-polarization for NbC/Fe and M23C6/Fe interfacial energ...

We present our results for the concurrent precipitation of the metastable M23C6, the Nb(C,N) secondary precipitates, and the Nb(C,N) primary crystals in 347H austenitic stainless steel. For precipitation modeling, we accounted for the elastic contribution to interfacial energy and for the Fe-spin-polarization for NbC/Fe and M23C6/Fe interfacial ene...

In the oxidative dehydrogenation (ODH) of alkanes, some important advances of the last decade have made it possible to accelerate the development and industrial insertion of the M1 based catalytic systems. These catalysts may be fine-tuned to account for the inevitable variability of different chemicals and impurities in the feedstocks. The latter...

Earlier experimental work on materials used in radioisotope thermoelectric generators (RTG) has shown that the Ir DOP-26 cladding material experiences intensified grain growth due to the unpinning of grain boundaries and diffusion of thorium to the surface of the material. This phenomenon has shown considerable dependence on high temperature enviro...

The original version of this article unfortunately contained an error. The authors would like to correct the error with this erratum.

Earlier experimental work on materials used in radioisotope thermoelectric generators (RTG) has shown that the Ir DOP-26 cladding material experiences intensified grain growth due to the unpinning of grain boundaries and diffusion of thorium to the surface of the material. This phenomenon has shown considerable dependence on high temperature enviro...

Accepted for publication in Topics in Catalysis on July 07, 2020

To assess whether a given temperature and holding time are benign for SNF drying, a series of thermodynamic and kinetic modeling runs were performed. For each aluminum alloy used in fuel elements, recommendations of an optimal drying temperature and duration of the drying treatment were made. Potential aluminum alloy cladding degradation mechanisms...

To accurately model the mesoscale oxidation behavior of metals and alloys, it is necessary to develop reliable thermodynamic and kinetic databases for the alloy systems containing oxygen. As the first step, the goal of these subtasks is to perform a gap analysis on existing thermodynamic and mobility databases for the Ni-Fe-Al-Cr-O model system. Th...

Glazoff, M.V. Integr Mater Manuf Innov (2019), https://doi.org/10.1007/s40192-019-00142-7 We present the original results pertaining to understanding topographical features on real industrial alloy surfaces. Quite often, such materials are subjected to different thermomechanical treatments with the goal of improving their yield strength, ductilit...

see the link: https://authors.elsevier.com/c/1ZKat_Ky~Fa3xr it will be available for only 40 days or so. Alloy 709 is an austenitic stainless steel with potential for structural applications in advanced nuclear reactors.In this study,creep tests on Alloy 709 specimens were performed at temperature of 700°C under applied stresses in the range of 12...

This paper describes recent work performed to assess the degradation of aluminum spent nuclear fuel (ASNF) as part of an ongoing Department of Energy project. As part of a multi-task effort, this paper specifically describes efforts initiated in 2018 to better understand chemical phenomena and degradation in ASNF). In this paper experimental and mo...

In 2017, a report was prepared by the Spent Nuclear Fuel Working Group in 2017 and titled “Technical Considerations and Challenges for Extended (>50 Years) Dry Storage” [1,2]. In this report several key scientific issues were identified pertaining to the problem of aluminum spent nuclear fuel (ASNF) and its safe removal from wet storage with subseq...

The 2nd edition of the "Casting Aluminum Alloys" originally published by Elsevier, Rotterdam, in 2007. The book has been revised extensively with the emphasis upon computer modeling techniques employed today at all stages of foundry aluminum alloys design and production. The list of the used/reviewed techniques includes atomic/electronic structure...

Computational Materials Science and its powerful modeling techniques were considered with in the framework of the ICME approach. The work flow is from "proto-data" (experiment, DFT) to Property-Specific Modeling Data (Thermo-Calc, DICTRA, PRISMA, Precipicalc(R), JMatPro(R), MICRESS(R), INL-proprietary MOOSE software) to "Meta-data" (i.e. data about...

Two types of flow-assisted corrosion were observed at Advanced Test Reactor (ATR) during PALM Cycle 153B-1 (April 2013) – pitting corrosion and erosion corrosion. In this paper, their description is provided along with the results of thermodynamic, kinetic, neutronics, and thermo-hydraulics modeling. Together, these results provide a plausible expl...

The Transient Reactor Test (TREAT) facility resides at the Materials and Fuels Complex (MFC) at Idaho National Laboratory (INL). TREAT first achieved criticality in 1959, and successfully performed many transient tests on nuclear fuel until 1994 when its operations were suspended. Resumption of operations at TREAT was approved in February 2014 to m...

Morphological synthesis operations were employed for understanding electrode microstructure transformations and evolution accompanying the application of charge/discharge cycles to electrochemical storage systems (batteries). Using state-of-the-art morphological algorithms, it was possible to predict microstructure evolution in porous Si electrodes...

The Transient Reactor Test (TREAT) facility resides at the Materials and Fuels Complex (MFC) at Idaho National Laboratory (INL). TREAT first achieved criticality in 1959, and successfully performed many transient tests on nuclear fuel until 1994 when its operations were suspended. Resumption of operations at TREAT was approved in February 2014 to m...

Advanced Test Reactor (ATR) Cycle 153B-1 was a 14-day, high-power, powered axial locator mechanism (PALM) operating cycle that completed on April 12, 2013. Cycle 153B-1 was a typical operating cycle for the ATR and did not result in any unusual plant transients. ATR was started up and shut down as scheduled. The PALM drive physically moves the sele...

The Transient Reactor Test (TREAT) facility that resides in the Materials and Fuels Complex (MFC) at Idaho National Laboratory (INL) first achieved criticality in 1959, and successfully performed many transient tests on nuclear fuel until 1994 when its operations were suspended1. Resumption of operations at TREAT was approved in February 2014 to me...

Transition aluminas doped with Cr find widespread application in the dehydrogenation catalysis industry, while La-stabilized transition aluminas are used extensively for high-temperature application as catalytic supports (Wefers and Misra in Oxides and hydroxides of aluminum, Alcoa Laboratories, Pittsburgh, 1987). In this work, detailed synchrotron...

Transition aluminas doped with Cr find widespread application in the dehydrogenation catalysis industry, while La-stabilized transition aluminas are used extensively for high temperature application as catalytic supports [1]. In this work, detailed synchrotron XAFS-spectroscopy studies were conducted to shed light upon the atomic mechanisms of surf...

Embodiments discussed herein in the form of methods, systems, and computer-readable media deal with the application of advanced “projectional” morphological algorithms for solving a broad range of problems. In a method of performing projectional morphological analysis an N-dimensional input is supplied. At least one N-dimensional form indicative of...

The issue of materials selection for many engineering applications represents an important problem, particularly in cases where material failure is possible as a result of corrosive environments. For example, 304 dual purpose or 316 stainless steel is used in the construction of many used nuclear fuel storage canisters. Deployed all over the world,...

Grade 91 steel (modified 9Cr-1Mo steel) is considered a prospective material for the Next Generation Nuclear Power Plant for application in reactor pressure vessels at temperatures of up to 650 °C. In this study, heat treatment of Grade 91 steel was performed by normalizing and tempering the steel at various temperatures for different periods of ti...

In the post-Fukushima world, the thermal and structural stability of materials under extreme conditions is an important issue for the safety of nuclear reactors. Because the nuclear industry is going to continue using advanced zirconium cladding materials in the foreseeable future, it becomes critical to gain fundamental understanding of the severa...

An evaluation of thermodynamic aspects of hot corrosion of the superalloys Haynes 242 and HastelloyTM N in the eutectic mixtures of KF and ZrF4 is carried out for development of Advanced High Temperature Reactor (AHTR). This work models the behavior of several superalloys, potential candidates for the AHTR, using computational thermodynamics tool (...

ABSTRACT: The modified 9Cr-1Mo steel (Grade 91) is a material of choice in fossil-fuel-fired power plants with increased efficiency, service life, and reduction in emission of greenhouse gases. It is also considered a prospective material for the Next Generation Nuclear Power Plant for application in reactor pressure vessels at temperatures up t...

Vaporization of Cr-rich volatile species from interconnect materials is a major source of degradation that limits the lifetime of planar solid oxide devices (solid oxide fuel cells and solid oxide electrolysis cells) with metallic interconnects. Some metallic coatings (Ni, Co, and Cu) may significantly reduce the Cr release from interconnects and s...

Vaporization of Cr-rich volatile species from interconnect materials is a major source of degradation that limits the lifetime of planar solid oxide devices (solid oxide fuel cells and solid oxide electrolysis cells) with metallic interconnects. Some metallic coatings (Ni, Co, and Cu) may significantly reduce the Cr release from interconnects and s...

This report documents the development, demonstration and validation of a mesoscale, microstructural evolution model for simulation of zirconium hydride δ-ZrH1.5 precipitation in the cladding of used nuclear fuels that may occur during long-term dry storage. While the Zr-based claddings are manufactured free of any hydrogen, they absorb hydrogen dur...

In the after-Fukushima world, the stability of materials under extreme conditions is an important issue for the safety of nuclear reactors. Among the methods explored currently to improve zircaloys’ thermal stability in off-normal conditions, using a protective coat of the SiC filaments is considered because silicon carbide is well known for its re...

g r a p h i c a l a b s t r a c t The ''checker board'' configuration for O atoms in octahedral interstitials. Zr atoms are shown in cyan, O in the first layer – in red, O in the second layer – in pink. Four non-equivalent groups of interstitials are indicated by numbers and yellow arrows. The formation of such ''suboxide'' ordered atomic structure...

In the after-Fukushima world, the stability of materials under extreme conditions is an important issue for the safety of nuclear reactors. Among the methods explored currently to improve zircaloys' thermal stability in off-normal conditions, using a protective coat of the SiC filaments is considered because silicon carbide is well known for its re...

Zirconium-based alloys Zircaloy-2 and Zircaloy-4 are widely used in nuclear industry as cladding materials for BWRs and PWRs, respectively. Over more than 60 years these materials displayed a very good combination of properties such as low neutron absorption, creep behavior, stress-corrosion cracking resistance, reduced hydrogen uptake, corrosion,...

ABSTRACT In this report (prepared in collaboration with Prof. Jeong Whan Yoon, Deakin University, Melbourne, Australia) a research effort was made to develop a non-associated flow rule for zirconium. Since Zr is a hexagonally close packed (HCP) material, it is impossible to describe its plastic response under arbitrary loading conditions with any a...

Computational Thermodynamic Modeling of Hot Corrosion of Alloys Haynes 242 and HastelloyTM N for Molten Salt Service in Advanced High Temperature Reactors An evaluation of thermodynamic aspects of hot corrosion of the superalloys Haynes 242 and HastelloyTM N in the eutectic mixtures of KF and ZrF4 is carried out for development of Advanced High Tem...

This presentation will discuss capacity fade issues and how advanced mathematical morphology computational methods can be used to identify changes which occur in electrode systems. A key advantage to using the advanced morphological analysis is the ability to monitor changes which occur, but which are not directly discernible to the eye allowing co...

This report satisfies a level 2 milestone for the Used Fuel Campaign’s (UFD’s) Science and Technology, Engineering Analysis of Storage and Transportation Project. It demonstrates a meso-scale, microstructural evolution model for simulation of zirconium hydride precipitation in the cladding of used fuels during long-term dry-storage. While the Zr-ba...

Zirconium-based alloys Zircaloy-2 and Zircaloy-4 are widely used in the nuclear industry as cladding materials for light water reactor (LWR) fuels. These materials display a very good combination of properties such as low neutron absorption, creep behavior, stress-corrosion cracking resistance, reduced hydrogen uptake, corrosion and/or oxidation, e...

This work deals with the computational thermodynamics and diffusion modeling of the superalloys to be used in Advanced High Temperature Reactor (AHTR). While the conventional approach involves expensive experimental work on diffusion (especially its scale-up) and hot corrosion of materials in molten salt eutectic mixtures, the computational thermod...

This technical evaluation (TEV) has been prepared to evaluate probable causes of the accident with Molten Salt Gasifier for hydrogen production. The accident happened when the new sparger was tested for work in molten salt environment when external pressure in the sparger increased up to ~70 to 100 psi. As a result of the accident, a violent outbur...

The product distribution of the Fischer−Tropsch (FT) process demonstrates a strong dependence upon the choice of catalyst, catalytic support, and reaction temperature. To develop understanding of the factors that underpin catalytic activity, we performed density-functional-theory (DFT)-based first-principles calculations for syngas reaction over bi...

The goal of next generation reactors is to increase energy ef?ciency in the production of electricity and provide high-temperature heat for industrial processes. The ef?cient transfer of energy for industrial applications depends on the ability to incorporate effective heat exchangers between the nuclear heat transport system and the industrial pro...

or the results of such use, of any information, apparatus, product or process disclosed in this report, or represents that its use by such third party would not infringe privately owned rights. The views expressed in this paper are not necessarily those of the United States Government or the sponsoring agency. ABSTRACT Stability of cladding materia...