Hydrogen Burden from the Steam Side Corrosion in Sodium-Heated Steam Generators

Roy, Prodyot; Rodgers, Douglas N.

doi:10.13182/nt78-a32080

Cited by 10 publications

(8 citation statements)

References 1 publication

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“…Because the steam oxidation proceeded during the first start-up test and the second start-up test, which was approximately 50 days, the result of the hydrogen flux in Figure 4 is actually comparable to the results between 50 and 130 days in Table 2. Moreover, the time to reach steady hydrogen flux agrees with the duration of approximately 2000 h that was proposed by Roy et al [1].…”

Section: Time Dependence Of Hydrogen Fluxsupporting

confidence: 88%

“…Table 3 (CGVS, Phenix, 50MWSGTF, Prototype Fast Reactor). The hydrogen flux obtained in the temperature range from 473 to 753 K agreed well with the hydrogen fluxes of other FBRs and facilities in the temperature range from 603 to 653 K [1,14], and also followed the Arrhenius relation. The agreement among the data is remarkable, considering that the operating conditions and the measurement methods and analysis of the hydrogen flux were different in each case.…”

Section: Steam Temperature Dependence Of Hydrogen Fluxsupporting

confidence: 75%

“…Hydrogen concentrations in sodium are controlled to low levels by continuous cold trapping and are monitored by online plugging meters to prevent precipitation in narrow pipes that can lead to sodium flow blockage. Hydrogen is also applicable to the nuclear safety operation of FBRs in two ways: (1) water leak detection and (2) tritium control. The early detection of water leaks in a steam generator (SG) is achieved by evaluation of a small rise in hydrogen concentrations from a low and stable background hydrogen level.…”

Section: Introductionmentioning

confidence: 99%

“…It has been determined by the hydrogen concentration rise rate in the sodium coolant, which was measured by shutting off the cold trap. Roy et al [1] collected these hydrogen fluxes obtained in some FBRs. It was proposed for an initial 2000 h, which was the average time required to reach steady state.…”

Section: Introductionmentioning

confidence: 99%

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Hydrogen flux through the heat transfer tube wall in the steam generator of Monju

Doi

Nakagiri

2013

Journal of Nuclear Science and Technology

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In fast breeder reactors (FBRs), hydrogen, one of the major impurities in sodium coolant, is used for water leak detection and tritium control in the interest of operating nuclear plant safety. It is essential to evaluate the hydrogen flux into the sodium coolant through the heat transfer tubes in a steam generator to understand the hydrogen behavior in an FBR plant. This study shows the time and temperature dependence of hydrogen flux using data obtained in the power rising test of the prototype FBR, Monju, and using the analysis code that can simulate the hydrogen distribution in an FBR plant. The hydrogen flux evaluated by the code gradually decreased with operating time, following the parabolic oxidation law and the Arrhenius relation over a wide range of steam temperatures. The results agreed with the hydrogen fluxes of other FBR plants evaluated in the past. It was also found that the hydrogen flux was mainly controlled by permeation through the heat transfer tubes, rather than the corrosion at the water side of the heat transfer tubes.

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Section: Time Dependence Of Hydrogen Fluxsupporting

confidence: 88%

Section: Steam Temperature Dependence Of Hydrogen Fluxsupporting

confidence: 75%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Hydrogen flux through the heat transfer tube wall in the steam generator of Monju

Doi

Nakagiri

2013

Journal of Nuclear Science and Technology

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“…To obtain a rational extrapolation which wotild be applied to design allowables, an estimate was obtained from the hydrogen permeation rate on the sodium side of the sodium heated steam generators. Roy and Rodgers (18) have collected steady-state hydrogen permeation rate data from various operating LMFBR steam generators. Furthermore, it has been shown that most of the hydrogen produced by corrosion according to eq.…”

Section: Via3 Aqueous Corrosionmentioning

confidence: 99%