Nanoscale characterization of HT-9 exposed to lead bismuth eutectic at 550°C for 3000h

Hosemann, Peter; Hawley, M. E.; Koury, Daniel; Welch, J.; Johnson, Allen L.; Mori, Gregor; Li, N.; Maloy, S.A.

doi:10.1016/j.jnucmat.2008.03.018

Cited by 18 publications

(15 citation statements)

References 10 publications

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“…The AFM technique applied in this report was developed in 1980s. Hosemann reported the application of AFM, MFM [5] and C-AFM [9] techniques to ferritic/martensitic (HT-9) and austenitic (D9) steel samples corroded in LBE. C-AFM is a contact-mode electrical characterization technique between the conductive AFM tip and the sample surface, by which variations in the local electrical properties are monitored in a range of pA to lA.…”

Section: Spm Analysesmentioning

confidence: 99%

HCM12A oxide layer investigation using scanning probe microscope

Kikuchi

Rivai²,

Saito³

et al. 2012

Journal of Nuclear Materials

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Section: Spm Analysesmentioning

confidence: 99%

HCM12A oxide layer investigation using scanning probe microscope

Kikuchi

Rivai²,

Saito³

et al. 2012

Journal of Nuclear Materials

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“…By carefully controlling the oxygen concentration in the LBE coolant, it is possible to maintain an iron and chromium based oxide film on the structural surfaces while keeping lead and bismuth from excessive oxidization that can lead to precipitation contamination. HT-9 (e.g., [51,52] ), T-91 (e.g., [53,54] ), T-410 (e.g., [51,55] ), and EP823 (e.g., [53] ). [34] The oxygen control technology has been well developed, including the control method (e.g., [37][38][39] ) and oxygen concentration measurement (e.g., [39][40][41] ).…”

Section: Lbe Corrosionmentioning

confidence: 99%

Lead–Bismuth Eutectic (LBE): A Coolant Candidate for Gen. IV Advanced Nuclear Reactor Concepts

Zhang

2013

Adv Eng Mater

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LBE is one of the primary coolant candidates of advanced nuclear reactors. The present review conducts an assessment of the coolant based on a series of liquid metal coolant selection criteria first and then identifies the key concerns of using LBE as the primary coolant of a nuclear reactor. The review focuses on the status of the art of these key concerns: materials degradation, protective oxide layer, and polonium production and control in an LBE coolant system. The review also addresses oxidation kinetics of steels in oxygen-containing LBE, development of oxygen technology and comparisons between LBE and liquid sodium.

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“…The entire tensile sample has an activity of 7.6×10 7 Bq, leading to volumetric activity rate of 2.49×10 9 Bq/cm 3 . A rather large FIB machined LEAP sample is a cone with a 3 μm height, 1 μm base diameter and volume of 0.785× 10 −12 cm 3 .…”

Section: Dose Rate and Isotope Estimations On The Stip Samplesmentioning

confidence: 99%

“…HT-9 is considered for in core structural components in the USA because of its substantial dataset on radiation induced property changes [2][3][4][5]. In addition, the performance of HT-9 in contact with lead bismuth eutectic coolants has been examined in relevant fast reactors environments [6,7]. After the actual STIP irradiation the samples were stored for a period of 62 month in order to allow for a decay of the shorter lived isotopes.…”

Section: Introductionmentioning

confidence: 99%

Large and Small Scale Materials Testing of HT-9 Irradiated in the STIP Irradiation Program

et al. 2010

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The Fuel Cycle R&D (FCRD) initiative is investigating methods of burning minor actinides in a transmutation fuel. To achieve this goal, the fast reactor core materials must withstand very high doses. Small scale materials testing methods in addition to large scale materials testing allows one to gain more insight by providing more data on the same sample while being able to probe areas of interest which are not accessible otherwise. Furthermore, the sample volumes were so small that the tests could be considered a non destructive test since the amount of material needed is so small that a macroscopic structure would not be affected. Tensile testing, micro hardness testing and micro compression testing on focused ion beam (FIB) microscope manufactured pillars were performed on remaining parts of tensile test specimens tested and irradiated in the Spallation Target Irradiation Program (STIP). It is shown that the increases of yield strength measured by tensile testing, micro compression testing and micro hardness testing all showed the same trend. In addition FIB based techniques also allowed fabrication of LEAP samples of such a small size that their residual activity was below detectable levels thus allowing them to be handled and analyzed in a manner comparable to inactive specimens.Keywords Micro compression testing . Atom probe tomography (ATP) . Local electrode atom probe (LEAP) .

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Nanoscale characterization of HT-9 exposed to lead bismuth eutectic at 550°C for 3000h

Cited by 18 publications

References 10 publications

HCM12A oxide layer investigation using scanning probe microscope

HCM12A oxide layer investigation using scanning probe microscope

Lead–Bismuth Eutectic (LBE): A Coolant Candidate for Gen. IV Advanced Nuclear Reactor Concepts

Large and Small Scale Materials Testing of HT-9 Irradiated in the STIP Irradiation Program

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