Considerations of Alloy N for Fluoride Salt-Cooled High-Temperature Reactor Applications

Ren, Weiju; Muralidharan, Govindarajan; Wilson, Daniel A.; Holcomb, David Eugene

doi:10.1115/pvp2011-57029

Cited by 45 publications

(21 citation statements)

References 0 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…These issues have been reviewed by Ren et al (2011) and are not addressed in this work. Here are some recommendations:…”

Section: Recommendationsmentioning

confidence: 99%

Technology Development Roadmap for the Advanced High Temperature Reactor Secondary Heat Exchanger

Sabharwall¹,

McCllar²,

Siahpush³

et al. 2012

View full text Add to dashboard Cite

Date v EXECUTIVE SUMMARYThis Technology Development Roadmap (TDRM) study presents the path forward for deploying large-scale molten salt secondary heat exchangers and presents the benefits of using molten salt as the heat transport medium for advanced high temperature reactors. The roadmap will aid in the development and selection of the required heat exchanger for power production (the first anticipated process heat application), and other process heat applications, such as, hydrogen, methanol to gasoline, and ammonia production. It also (a) establishes the current state of readiness for molten salt secondary heat exchanger technology, (b) defines a path forward that systematically and effectively tests this technology to overcome areas of uncertainty, (c) demonstrates the achievement of an appropriate level of maturity prior to construction and plant operation, and (d) identifies issues and prioritizes future work for maturing the state of secondary heat exchangers technology.The TDRM was developed to identify the research and development activities, modeling, design, fabrication, and scaled testing that must occur to satisfy the requirements of advancing technological readiness. TDRMs provide the framework and structure required to systematically perform decision analysis, reduce risk, and mature technologies in a cost effective and timely manner. The roadmap uses the Technology Readiness Level (TRL) as a measure of the level of technical maturity of a technology, that is, the ability to design, fabricate, and deploy a component or system. The Secondary Heat Exchanger (SHX) is currently at a TRL-3 and the challenges addressed in this study must be overcome to mature this technology into a viable and reliable heat transfer system. Also addressed in this study is the potential future work, which will help in further enhancing the SHX TRL.This study discusses the results of a preliminary design analysis of the SHX. The efficient transfer of energy for industrial applications depends on the ability to incorporate cost-effective heat exchangers between the nuclear heat transport system and industrial process heat transport system. The heat exchanger required for AHTR is subjected to a unique set of conditions that bring with them several design challenges not encountered in standard heat exchangers. The somewhat corrosive molten salts, especially at higher temperatures, require materials throughout the system to avoid corrosion, and adverse high-temperature effects such as creep.Fuels salts received considerable testing and development in the Molten Salt Reactor Experiment (MSRE) program at Oak Ridge National Laboratory during the 1950s through 1970s, but relatively little research has been conducted on coolant salts. The corrosion data for various alloys in coolant salts (i.e., FLiBe, FLiNaK, KCl-MgCl 2 , NaNO 2 -NaNO 3 -KNO 3 and KF-ZrF 4 ) are too limited for reliable comparisons of corrosion resistance of the various alloys, or the relative aggressiveness of these molten salts.Tritium produced in the Advanced ...

show abstract

“…These issues have been reviewed by Ren et al (2011) and are not addressed in this work. Here are some recommendations:…”

Section: Recommendationsmentioning

confidence: 99%

Technology Development Roadmap for the Advanced High Temperature Reactor Secondary Heat Exchanger

Sabharwall¹,

McCllar²,

Siahpush³

et al. 2012

View full text Add to dashboard Cite

show abstract

“…During the early Aircraft Nuclear Propulsion program (LeBlanc, 2010), which proposed using salt as a heat transfer medium, it was found that levels of chromium traditionally used for oxidation resistance in high temperature service showed accelerated corrosion in molten salt. The eventual solution was a nickel-based alloy originally developed at Oak Ridge National Laboratory and eventually produced by Haynes as Hastelloy N, with chromium reduced to about 8%, and a significant addition of molybdenum (16%) (White, 2010), (Ren, Muralidharan, Wilson, & Holcomb, July 17-21, 2011), (Sessions & Lundy, 1969), (Wilson, 2010).…”

Section: Molten Salt Servicementioning

confidence: 99%

Diffusion Welding of Alloys for Molten Salt Service - Status Report

Clark¹,

Mizia²,

Sabharwall³

2012

View full text Add to dashboard Cite

This report addresses present work concerned with heat exchanger development for molten salt service, including the AHTR (Advanced High Temperature Reactor), which uses molten salt for cooling and process heat transfer. These results are an outgrowth of recent work done under the Next Generation Nuclear Plant (NGNP) Project, which was concerned with the diffusion welding of Alloys 800H, 617, and similar materials for oxidation resistance at operating temperatures up to 900 °C. The molten salt systems discussed herein use other alloys such as Alloy N and 242, which show corrosion resistance to molten salt at nominal operating temperatures up to 700 °C. These alloys were diffusion welded, typically at 1150 °C for 3 hours under applied loads of ~5 MPa using the Gleeble thermomechanical testing machine. Thermocalc/DICTRA models were developed to predict diffusion, and compositions of welds with a 15 µm nickel foil interlayer were measured after welding for comparison. Calculated and experimental values were in good agreement. Test specimens were prepared for exposing diffusion welds to molten salt environments. Alloy N and 242 were found to be weldable by diffusion welding, with ultimate tensile strengths about 90% of base metal values. Both diffusion welds and sheet material in Alloy N were corrosion tested in 58 mol% KF/42 mol%ZrF 4 at 650, 700, and 850 °C for 200, 500, and 1000 hours. Corrosion rates were similar between welded and nonwelded materials, typically <10 mils per year.

show abstract

“…During the early Aircraft Nuclear Propulsion program (LeBlanc, 2010), which proposed using salt as a heat transfer medium, it was found that levels of chromium traditionally used for oxidation resistance in high temperature service showed accelerated corrosion in molten salt. The eventual solution was a nickel-based alloy originally developed at Oak Ridge National Laboratory and eventually produced by Haynes as Hastelloy N, with chromium reduced to about 8%, and a significant addition of molybdenum (16%) (White, 2010), (Ren, Muralidharan, Wilson, & Holcomb, 2011), (Sessions & Lundy, 1969), (Wilson, 2010).…”

Section: Molten Salt Servicementioning

confidence: 99%

Diffusion Welding of Alloys for Molten Salt Service - Status Report

Clark¹,

Mizia²

2012

View full text Add to dashboard Cite

This report addresses present work concerned with heat exchanger development for molten salt service, including the AHTR (Advanced High Temperature Reactor), which uses molten salt for cooling and process heat transfer. These results are an outgrowth of recent work done under the Next Generation Nuclear Plant (NGNP) Project, which was concerned with the diffusion welding of Alloys 800H, 617, and similar materials for oxidation resistance at operating temperatures up to 900°C. The molten salt systems discussed herein use other alloys such as Alloy N and 242, which show corrosion resistance to molten salt at nominal operating temperatures up to 700°C. These alloys were diffusion welded, typically at 1150°C for 3 hours under applied loads of ~5 MPa using the Gleeble thermo-mechanical testing machine. Thermocalc/DICTRA models were developed to predict diffusion, and compositions of welds with a 15 µm nickel foil interlayer were measured after welding for comparison. Calculated and experimental values were in good agreement. Test specimens were prepared for exposing diffusion welds to molten salt environments. Alloy N and 242 were found to be weldable by diffusion welding, with ultimate tensile strengths about 90% of base metal values.

show abstract

Considerations of Alloy N for Fluoride Salt-Cooled High-Temperature Reactor Applications

Cited by 45 publications

References 0 publications

Technology Development Roadmap for the Advanced High Temperature Reactor Secondary Heat Exchanger

Technology Development Roadmap for the Advanced High Temperature Reactor Secondary Heat Exchanger

Diffusion Welding of Alloys for Molten Salt Service - Status Report

Diffusion Welding of Alloys for Molten Salt Service - Status Report

Contact Info

Product

Resources

About