Hydrogen Production with a High-Temperature Gas-Cooled Reactor (HTGR)

Quade, R.N.; McMain, A.T.

doi:10.1007/978-1-4684-2607-6_10

Cited by 8 publications

(5 citation statements)

References 1 publication

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“…A high-temperature gas-cooled reactor (HTGR) uses helium gas as a coolant and a has very high outlet temperature exceeding 750 °C. HTGRs provide high efficiency in power generation and enable process heat applications such as hydrogen production [51]. 2Cr…”

Section: High-temperature Gas-cooled Reactorsmentioning

confidence: 99%

Corrosion Testing Needs and Considerations for Additively Manufactured Materials in Nuclear Reactors

Jokisaari,

Chen,

Hartmann

et al. 2023

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The Advanced Materials and Manufacturing Technologies (AMMT) program within the Department of Energy, Office of Nuclear Energy (DOE-NE) has developed its current recommendation for its corrosion testing strategy to deploy additively manufactured (AM) materials in advanced nuclear reactors. Additive manufacturing technologies have developed rapidly in recent years, creating new opportunities and challenges for the nuclear industry. To adopt AM technologies, the corrosion performance of AM materials needs to be adequately evaluated.This document is divided into seven chapters designed to support the proposed corrosion research strategy. The strategy focuses on the testing of AM 316H stainless steel (SS) to align with the broader AMMT program. An overview of localized and uniform corrosion mechanisms and their synergy with other degradation modes is provided. Specifically, the corrosion resistance of 316H is largely provided by the presence of an intact chromium oxide film on the surface, and loss or damage of this film is generally responsible for corrosion degradation.Engineering concerns for corrosion behavior are discussed, including component failure mechanisms and corrosion codes and standards. While the standards are extensive, certain material testing standards do not exist that would be relevant for the AMMT program. Reactor-specific corrosion concerns for molten salt reactors, liquid metal-cooled reactors, and high-temperature gas reactors will guide corrosion testing. Key factors likely to influence corrosion properties of AM materials (especially 316H) include build porosity, the presence of unusual phases, residual stress, microsegregation within the cellular substructure, and surface roughness. Post-build treatments and process variability need to be assessed with multiple specimens that are microstructurally quantified to develop structureproperty-performance relationships with uncertainty quantification. Sufficient facilities exist, at least for initial program efforts focusing on characterization of unirradiated material in laboratory settings, across Argonne National Laboratory

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Section: High-temperature Gas-cooled Reactorsmentioning

confidence: 99%

Corrosion Testing Needs and Considerations for Additively Manufactured Materials in Nuclear Reactors

Jokisaari,

Chen,

Hartmann

et al. 2023

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show abstract

“…The High Temperature Gas (cooled) Reactor (HTGR) may be the most appropriate and a possible economical source of energy for thermochemical cycles (5,73,75).…”

Section: Chemical Reactionmentioning

confidence: 99%

The kinetics of the reverse deacon reaction

Nanda

1988

International Journal of Hydrogen Energy

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“…High-temperature gas-cooled reactor (HTGR) is an advanced type of nuclear reactor. Nuclear reactors of this type are gaining more and more interest mainly due to their high thermal effi ciency, higher safety level, and cost effectiveness [1][2][3][4]. Nuclear fuel used in modern HTGRs consists of spherical uranium dioxide particles covered with a very durable coating consisting of porous pyrolytic carbon (PyC), dense PyC, silicon carbide, and the outer layer of dense PyC.…”

Section: Introductionmentioning

confidence: 99%

Critical comparison of INAA and ICP-MS applied in the characterization of purity of TRISO fuel and substrates to its production

Chajduk

Kalbarczyk

2021

Nukleonika

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The application of inductively coupled plasma mass spectrometry (ICP-MS), both in solution and laser ablation (LA) mode, and instrumental neutron activation analysis (INAA) in the nuclear material analysis are presented in this paper. The possibility of each technique for the chemical characterization of substances used during TRISO fuel production and its advantages and limitations are discussed based on the obtained results of the analysis of real materials used in TRISO fuel production in the Institute of Nuclear Chemistry and Technology. The paper also reports the application of INAA and LA-ICP-MS to the verification of the purity of the protective layers of pyrolytic carbon (PyC) and silicon carbide.

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Hydrogen Production with a High-Temperature Gas-Cooled Reactor (HTGR)

Cited by 8 publications

References 1 publication

Corrosion Testing Needs and Considerations for Additively Manufactured Materials in Nuclear Reactors

Corrosion Testing Needs and Considerations for Additively Manufactured Materials in Nuclear Reactors

The kinetics of the reverse deacon reaction

Critical comparison of INAA and ICP-MS applied in the characterization of purity of TRISO fuel and substrates to its production

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