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Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.

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At least 289 records · Page 16
All sourcesNASA NTRSDOE OSTI
DOE OSTI2015

STRESS CORROSION CRACKING OF A 52M WELD OVERLAY IN A PWR ENVIRONMENT

Weld overlays (WOL) of alloys believed to possess superior stress corrosion cracking (SCC) resistance due to their higher Cr content are typically applied over welds made with SCC-susceptible alloys with the expectation that they will act as a barrier to SCC. The objective of this work was to investigate the SCC behavior near or at the WOL interface. For this purpose, a 52M WOL was deposited on a double-J Alloy 182 weld using prototypical welding parameters. In the first set stage of this work, cracks were initiated in Alloy 182 and allowed to propagate in a direction perpendicular to the Alloy 52M WOL interface. Two identical tests conducted in this manner revealed that the average SCC propagation rates in Alloy 182 decreased by an order of magnitude to approx. 10-11 m/s by the time they reached the Alloy 52M interface, and that they continued to propagate past the interface into Alloy 52M at a similar rate. The post-test examination found that significant crack branching occurred at the interface between the two alloys, with SCC propagation along both the original direction into Alloy 52M and the interface between the two welds. Growth along the interface between the two welds was severe, with a rates estimated at approx. 10-10 m/s. While the average rate of propagation in Alloy 52M was measured to be in the 10-11 m/s range, the maximum SCC penetration into Alloy 52M was 2.5 mm which translates into an estimated maximum SCC rate an order of magnitude higher. Hence, in the second stage of this work – and this is the focus of this paper, confirmatory tests were conducted with the specimens aligned along the WOL interface. These tests substantiated the earlier findings: the SCC rate under constant load conditions at the interface between the two welds (20% Cr) was slightly faster than that in Alloy 52M near the interface (25% Cr), and both were in the 10-10 m/s range.

Alloy 52M↗
DOE OSTI2017

Modeling of Subcritical PWR with Fixed Neutron Source Using MPACT

Neutron source assembly inserts are used in some light water reactors (LWRs) during low flux subcritical conditions to ensure the excore source range detectors are both operational and responding to core multiplication neutrons. These source range detectors are used for sensing any approaches to criticality, either by controlled assent or accidental reactivity insertion (i.e. boron dilution event or unintended control rod withdrawal).

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2017

In-Situ Proton Irradiation-Corrosion Study of ATF Candidate Alloys in Simulated PWR Primary Water

Irradiation enhanced corrosion behavior of Accident Tolerant Fuel candidate alloys T91 and Fe15Cr4Al were evaluated using in-situ proton irradiation-corrosion experiments in hydrogenated pure water (at 320 °C, 3 wppm H2) with a 5.4 MeV proton beam. The thin sample acted as a “window” to allow protons to fully penetrate the sample while maintaining system pressure. The area of the samples exposed to the proton beam experienced effects from displacement damage and radiolysis products. The aim of the study was to characterize the effect of radiation on the kinetics and character of oxidation caused by accelerated waterside corrosion under irradiation. Samples irradiated with protons for total displacement damage of *0.1 dpa (dose rate in water, 400 kGy/s) at an exposure time of 24 h were compared. Oxide morphology, phase structure, and composition of the oxide, metal and the metal/oxide interface were investigated using TEM and EDS and are related to the test conditions. The oxidation rate or resulting oxide thickness is dependent on the alloy Cr content; the oxidation rate increased as the Cr content decreased. The resulting oxide consists of an inner layer of Cr-rich spinel oxide and outer magnetite crystals in the unirradiated region; while the irradiated region consists of Cr-rich inner oxide spinel that was partially dissolved and coverage of outer non-faceted hematite precipitates.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗
DOE OSTI2019

Effect of Material Condition on Stress Corrosion Crack Initiation of Cold-Worked Alloy 600 in Simulated PWR Primary Water

The effect of material condition and grain boundary (GB) carbides on stress corrosion crack (SCC) initiation was evaluated on a cold-worked Alloy 600 heat in the solution annealed and thermally treated conditions. SCC initiation response of these material conditions were investigated by constant load testing in simulated pressurized water reactor primary coolant environments. Direct current potential drop technique was used for in-situ detection of SCC initiation. With periodic examination of the specimens, evolution of precursor damage including intergranular attack and short cracks was carefully documented and compared to data previously obtained from unstressed coupons with the same material conditions and were exposed to the same environment. Results revealed a predominant role of mechanical factors in the development of precursor damage with no apparent improvement of GB carbides on SCC initiation resistance.

Zhai, Ziqing↗
DOE OSTI2019

Crack Initiation Behavior of Cold-Worked Alloy 690 in Simulated PWR Primary Water - Role of Starting Microstructure, Applied Stress and Cold Work on Precursor Damage Evolution

Long-term stress corrosion crack (SCC) initiation behavior in Alloy 690 is being evaluated by constant load tensile testing in simulated pressurized water reactor primary water. Seven commercial Alloy 690 heats with different starting microstructures and cold-work levels are being tested at either 90% or 100% of the material yield stress. Previous studies have revealed grain boundary (GB) cavity formation after 7,110 to 9,220 hours of exposure in certain thermally treated (TT) Alloy 690 heats in highly cold-worked (CW) conditions, serving as precursors to intergranular cracks. This paper summarizes the new characterization results for the evolution of GB cavities in four Alloy 690TT heats in 21% and 31%CW conditions loaded at yield stress after 18,400 hours of exposure. Link-up of GB cavities has led to formation of long internal creep cracks, resulting in crack initiation detected by direct current potential drop in a highly CW Alloy 690TT heat with uniform, semi-continuous distribution of small GB carbides. In comparison, highly CW materials featuring larger and more widely spaced GB carbides did not show a significant increase in GB cavity density or size. Quantitative assessments were performed on GB cavity evolution in highly CW specimens for two Alloy 690TT heats demonstrating the strong dependence of GB cavity evolution on applied stress and starting GB microstructure.

Zhai, Ziqing↗