Effect of high-temperature water and hydrogen on the fracture behavior of a low-alloy reactor pressure vessel steel

Roychowdhury, S.; Seifert, Hans-Peter; Spätig, P.; Que, Zaiqing

doi:10.1016/j.jnucmat.2016.05.033

Cited by 20 publications

(7 citation statements)

References 42 publications

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“…The normalized potential drop Usp,0/Uref,0 at the crack initiation point was assigned to the initial notch depth a0. In contrast to notched tensile specimens [42] in slow strain rate tests or pre-cracked specimens in slow rising load tests [43,44], the effect of the geometry change and blunting by plastic deformation and growth of plastic zone at the notch root on the DCPD potential drop in the sharply notched C(T) specimens under small scale yielding conditions in the rising load phase is very moderate. There is usually no or only a very small linear increase of Usp/Uref with the crack opening displacement at load line CODLL or load before crack initiation.…”

Section: Scc Initiation and Short Crack Growth Testsmentioning

confidence: 83%

Stress corrosion cracking initiation and short crack growth behaviour in Alloy 182 weld metal under simulated boiling water reactor hydrogen water chemistry conditions

et al. 2018

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The effect of dissolved hydrogen on the stress corrosion cracking initiation and short crack growth behaviour of Alloy 182 weld metal was evaluated in 274 °C hydrogenated high-purity water using accelerated crack initiation and growth tests with sharply notched fracture mechanics specimens and in-situ crack initiation and growth monitoring. A maximum in initiation susceptibility and crack growth rates was observed at the Ni/NiO phase transition line. Grain boundary misorientations and mismatch in Schmid factor were measured by electron backscattered diffraction along intergranular stress corrosion cracks and at crack initiation sites. Low angle boundaries seem to be particularly resistant to cracking.

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Section: Scc Initiation and Short Crack Growth Testsmentioning

confidence: 83%

Stress corrosion cracking initiation and short crack growth behaviour in Alloy 182 weld metal under simulated boiling water reactor hydrogen water chemistry conditions

et al. 2018

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“…From the above analysis, it is concluded that preferable cooling performance could be achieved by increasing the number of cooling tubes. Importantly, there may be an upper limit to the cooling tube quantities in combination with actual use, starting from the view of structural safety of tank body …”

Section: Resultsmentioning

confidence: 99%

“…Importantly, there may be an upper limit to the cooling tube quantities in combination with actual use, starting from the view of structural safety of tank body. 41…”

Section: Effect Of the Cooling Tube Patternmentioning

confidence: 99%

A three‐dimensional heat transfer model for thermal performance evaluation of ZrCo‐based hydride bed with embedded circular‐shaped cooling tubes

et al. 2019

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Summary Nowadays, metal hydrides are generally deemed as one of the most potential materials that are in favor of compact hydrogen storage for industrial applications. This work was committed to evaluate the thermal performance of a circular‐shaped‐tube thin double‐layered hydrogen storage reactor using a three‐dimensional model. Finite element simulations were conducted to systematically study the influences of structural geometries, cooling patterns, and material thermophysical properties on the heat diffusion behavior under the framework of convection heat transfer. The results indicate that the proposed model effectively characterizes temperature evolutions during hydrogen absorption process. Moreover, a statistical analysis was performed to reveal the sensitivity sequence of these factors on the total thermal performance, suggesting that decreasing the hydride layer thickness, increasing the number of U‐shaped cooling tubes, accelerating the cooling fluid flow rate, and enhancing the thermal conductivity are more beneficial to the thermal performance improvement. Detailed analysis confirms the possibility of developing the present hydrogen storage tank utilizing metal hydrides for engineering practice.

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“…Fabrication-or welding-induced incipient cracks (e.g., hot and relaxation cracks in the cladding or cladding/RPV interface) were observed in few isolated cases. Furthermore, the toughness and ductility of the RPV steel can decrease with time due to irradiation embrittlement, thermal ageing or potential (corrosive) reactor coolant (e.g., hydrogen) effects [5,6].…”

Section: Introductionmentioning

confidence: 99%

“…The SCC [7], strain-induced corrosion cracking (SICC) [8] and corrosion fatigue (CF) [9] crack growth behaviour of different low-alloy RPV steels and weldments/heat-affected zones (HAZ) and the SCC crack growth behaviour in the Alloy 182-RPV steel transition region of dissimilar metal welds (DMW) [3,4] under BWR normal water (NWC) and hydrogen water chemistry (HWC) conditions as well as the role of dynamic strain ageing (DSA) in EAC of low-alloy steels (LAS) [7,10] was therefore investigated at Paul Scherrer Institut (PSI) in detail in the last two decades. Currently, these investigations are extended to potential high-temperature water and hydrogen effects on the fracture toughness and tearing resistance of RPV steels [5,6]. SCC crack growth in RPV steels: The SCC behaviour of low-alloy steel (LAS) pressure boundary components under transient-free, steady-state BWR power operation conditions, which covers the largest part of the lifetime, is well established [1,2,7].…”

Section: Introductionmentioning

confidence: 99%

The influence of ppb levels of chloride impurities on the stress corrosion crack growth behaviour of low-alloy steels under simulated boiling water reactor conditions

Seifert

Ritter

2016

Corrosion Science

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The effect of chloride on the stress corrosion crack (SCC) growth behaviour in low-alloy reactor pressure vessel steels was evaluated under simulated boiling water reactor conditions. In normal water chemistry environment, ppb-levels of chloride may result in fast SCC after rather short incubation periods of few hours. After moderate and short-term chloride transients, the SCC crack growth rates return to the same very low high-purity water values within few 100 hours. Potential long-term (memory) effects on SCC crack growth cannot be excluded after severe and prolonged chloride transients. The chloride tolerance for SCC in hydrogen water chemistry environment is much higher.

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Effect of high-temperature water and hydrogen on the fracture behavior of a low-alloy reactor pressure vessel steel

Cited by 20 publications

References 42 publications

Stress corrosion cracking initiation and short crack growth behaviour in Alloy 182 weld metal under simulated boiling water reactor hydrogen water chemistry conditions

Stress corrosion cracking initiation and short crack growth behaviour in Alloy 182 weld metal under simulated boiling water reactor hydrogen water chemistry conditions

A three‐dimensional heat transfer model for thermal performance evaluation of ZrCo‐based hydride bed with embedded circular‐shaped cooling tubes

The influence of ppb levels of chloride impurities on the stress corrosion crack growth behaviour of low-alloy steels under simulated boiling water reactor conditions

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