The Permeation of Hydrogen Isotopes through Structural Metals at Low Pressures and through Metals with Oxide Film Barriers

Strehlow, Roger A.; Savage, H.C.

doi:10.13182/nt74-a16282

Cited by 118 publications

(33 citation statements)

References 11 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…It is hard to compare these results with data available in the literature due to the differences in the experimental arrangement and test conditions. The closest data given in Table 3 was found in the paper by Strehlow and Savage, 1974. In the present mock cell the surface area though which hydrogen may permeate is 144 cm2 and assuming the partial pressure of hydrogen outside the AMTEC cell is 1.0 torr (133 Pa, which is the partial pressure at 10% excess air, Table l), the correlations in Table 3 gives the permeation rate as 1.8 * lom5 cc/s.…”

Section: Test Proceduressupporting

confidence: 77%

“…Hydrogen permeation rates through thin (0.10" -0.028) stainless steel were calculated using a pressure gradient corresponding to the partial pressure of hydrogen in the flame and correlations from different authors (Strehlow and Savage, 1974;Birnbaum and Wert, 1972). In all cases the rates were high enough to cause problems to a Series II AMTEC cell in the long run.…”

Section: Problem Descriptionmentioning

confidence: 99%

“…Potential effects include depriming of the AMTEC cell arteries, blockage of the condenser and hydride formation. Numerous papers and reports have been published concerning hydrogen diffusion in solids (Birnbaum and Wert, 1972;Garber, 1975;Strehlow and Savage, 1974). Many of these papers concern the embrittling effects of hydrogen and many concern the diffusion process itself.…”

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Low Emission AMTEC Automotive Power System. Final report for Department of Energy Contract DE-FG02-94ER81696

Hunt¹

2001

View full text Add to dashboard Cite

Section: Test Proceduressupporting

confidence: 77%

Section: Problem Descriptionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Low Emission AMTEC Automotive Power System. Final report for Department of Energy Contract DE-FG02-94ER81696

Hunt¹

2001

View full text Add to dashboard Cite

“…4 and 9) in the ID of the cladding will significantly reduce the hydrogen permeation from the fuel to the coolant [25]. It has been shown that not only alumina would reduce permeation of tritium from the fuel to the coolant, other oxides will also reduce hydrogen or tritium permeation [26,27].…”

Section: Mitigation Measures To Neutron Absorption and Tritium Releasementioning

confidence: 99%

Iron-chrome-aluminum alloy cladding for increasing safety in nuclear power plants

Rebak

2017

EPJ Nuclear Sci. Technol.

View full text Add to dashboard Cite

Abstract. After a tsunami caused plant black out at Fukushima, followed by hydrogen explosions, the US Department of Energy partnered with fuel vendors to study safer alternatives to the current UO 2 -zirconium alloy system. This accident tolerant fuel alternative should better tolerate loss of cooling in the core for a considerably longer time while maintaining or improving the fuel performance during normal operation conditions. General electric, Oak ridge national laboratory, and their partners are proposing to replace zirconium alloy cladding in current commercial light water power reactors with an iron-chromium-aluminum (FeCrAl) cladding such as APMT or C26M. Extensive testing and evaluation is being conducted to determine the suitability of FeCrAl under normal operation conditions and under severe accident conditions. Results show that FeCrAl has excellent corrosion resistance under normal operation conditions and FeCrAl is several orders of magnitude more resistant than zirconium alloys to degradation by superheated steam under accident conditions, generating less heat of oxidation and lower amount of combustible hydrogen gas. Higher neutron absorption and tritium release effects can be minimized by design changes. The implementation of FeCrAl cladding is a near term solution to enhance the safety of the current fleet of commercial light water power reactors.

show abstract

“…Therefore, the effects of C H2;2nd and C HT;2nd on the tritium activity concentrations in the IS process were investigated parametrically in the relatively wide ranges from 1:0 Â 10 À3 to 100 volume ppm and from 1:0 Â 10 À6 to 1.0 volume ppb, respectively. (5) Permeability of Tritium and Hydrogen through Heat Transfer Tubes The development and selection of the corrosion resistance materials for the high-temperature components such as the 27,28) For the Peach Bottom HTGR, the first HTGR in the US, it was reported that the permeability of the steam generator was decreased by the oxide layer formed on the steam side surface.…”

Section: (4) Tritium and Hydrogen Concentrations In The Secondarymentioning

confidence: 99%

Numerical Study on Tritium Behavior by Using Isotope Exchange Reactions in Thermochemical Water-Splitting Iodine–Sulfur Process

Ohashi

Sakaba

Nishihara

et al. 2007

J. Nucl. Sci. Technol.

View full text Add to dashboard Cite

One potential problem in the hydrogen production system coupled with the high-temperature gascooled reactor (HTGR) is transmission of tritium from the primary coolant to the product hydrogen by permeation through the heat transfer tubes. Tritium accumulation in the process chemicals in the components of a hydrogen plant, a thermochemical water-splitting iodine-sulfur (IS) process, will also be a critical issue in seeking to license the hydrogen plant as a non-nuclear plant in the future. A numerical analysis model for tritium behavior in the IS process was developed by considering the isotope exchange reactions between tritium and the hydrogen-containing process chemicals, i.e., H 2 O, H 2 SO 4 and HI. The tritium activity concentration in the IS process coupled with the high-temperature engineering test reactor (HTTR), the HTTR-IS system, was preliminarily evaluated in regard to the effects of some indeterminate parameters, i.e., equilibrium constants of the isotope exchange reactions, permeability of tritium through heat transfer tubes, tritium and hydrogen concentrations in the secondary helium coolant, and the leak rate from the secondary coolant loop. The results describing how the tritium activity concentration changes with variations in these parameters and which component has the maximum tritium activity concentration in the IS process are described in this paper.

show abstract

The Permeation of Hydrogen Isotopes through Structural Metals at Low Pressures and through Metals with Oxide Film Barriers

Cited by 118 publications

References 11 publications

Low Emission AMTEC Automotive Power System. Final report for Department of Energy Contract DE-FG02-94ER81696

Low Emission AMTEC Automotive Power System. Final report for Department of Energy Contract DE-FG02-94ER81696

Iron-chrome-aluminum alloy cladding for increasing safety in nuclear power plants

Numerical Study on Tritium Behavior by Using Isotope Exchange Reactions in Thermochemical Water-Splitting Iodine–Sulfur Process

Contact Info

Product

Resources

About