Diffusion of Titanium in Modified Hastelloy N

Sessions, C.E.; Lundy, T.S.

doi:10.2172/12773547

Cited by 3 publications

(11 citation statements)

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“…The metal in the reactor vessel and in the primary piping will be exposed to molten fuel salt at temperatures up to 1300°F on one side and to the celt atmosphere (95% N z -5% O,) at 1000°F on the other. The anticipated service life is 30 years, owing which time the most highSy irradiated portions of the reactor vestd watt be exposed to * fast-pcutroa (t > 0.1 MeV) flueace of leas than I X 10*' neutrous/cm 3 and a thermal-neutron flueace of about 5 X 10" rteutrons/cm*.…”

Section: H E Mccoymentioning

confidence: 99%

“…The salt stream leaving the hydrofluorinator, which contains UF 4 and PaF 4 , passes through a fluorinator, where about 95% of the uranium is removed. The resulting salt stream then flows through a tank having a volume of about 130 ft 3 , where most of the protactinium is held and where most of the protactinium decay heat is removed. Uranium Materials that do not fcrm volatile fluorides during fluorination will also accumulate in the decay tank; these include fissic.i product zirconium and corrosion product nickel.…”

mentioning

confidence: 99%

“…Uranium Materials that do not fcrm volatile fluorides during fluorination will also accumulate in the decay tank; these include fissic.i product zirconium and corrosion product nickel. These materials are subsequently re moved from the tank by periodic discard of salt at a rate equivalent to about 0.1 ft 3 /day. In summary, in the protactinium isolation system, all the uranium that leaves the reactor, plus that produced by decay of the protactinium, appear?…”

mentioning

confidence: 99%

“…After fabrication, the pieces may be treated with a sealing process to increase the resistance to gas permeation, as discussed in Sect. 3 …”

mentioning

confidence: 99%

See 3 more Smart Citations

Conceptual Design Study of a Single-Fluid Molten-Salt Breeder Reactor.

Robertson¹

1971

189

113

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Section: H E Mccoymentioning

confidence: 99%

mentioning

confidence: 99%

mentioning

confidence: 99%

“…After fabrication, the pieces may be treated with a sealing process to increase the resistance to gas permeation, as discussed in Sect. 3 …”

mentioning

confidence: 99%

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Conceptual Design Study of a Single-Fluid Molten-Salt Breeder Reactor.

Robertson¹

1971

189

113

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“…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

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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.

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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.

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Diffusion of Titanium in Modified Hastelloy N

Cited by 3 publications

References 0 publications

Conceptual Design Study of a Single-Fluid Molten-Salt Breeder Reactor.

Conceptual Design Study of a Single-Fluid Molten-Salt Breeder Reactor.

Diffusion Welding of Alloys for Molten Salt Service - Status Report

Diffusion Welding of Alloys for Molten Salt Service - Status Report

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