R. Klueh

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Thermal Aging Effects on the Mechanical Properties of Annealed 21/4 Cr-1 Mo Steel

Analysis of swelling behaviour of ferritic/martensitic steels

Philosophical Magazine

Mechanical properties of a 2-1/4 Cr-1 Mo steel tubesheet forging

Journal of Materials for Energy Systems

Microstructural evolution of HFIR-irradiated low activation F82H and F82H-{sup 10}B steels

The development of ferritic steels for fast induced-radioactivity decay for fusion reactor applications

Fusion Engineering and Design

The Cr-Mo ferritic (martensitic) steels are leading candidates for the structural components for ... more The Cr-Mo ferritic (martensitic) steels are leading candidates for the structural components for future fusion reactors. However, irradiation of such steels in a fusion environment produces long-lived radioactive isotopes that lead to difficult waste disposal problems once the structure is removed from service. One method proposed to alleviate such problems is the development of steels that contain only elements that produce radioactive isotopes that decay to low levels in a reasonable time (tens of years instead of hundreds or thousands of years). For such a solution for the Cr-Mo steels, molybdenum must be eliminated. In addition, niobium must be maintained at extremely low levels. Tungsten is proposed as an appropriate substitution for molybdenum, and the procedures for developing Cr-W steels analogous to the Cr-Mo steels are discussed.

format_quoteInitial concentration limits for alloy elements were proposed based on radioactive waste classification guidelines post-reactor shutdown.format_quote

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Microstructure and Hardness Variation in a TIG Weldment of Irradiated F82H

Fusion Science and Technology

Previous work reported that a TIG weld joint of F82H exhibited low irradiation hardening in a ten... more Previous work reported that a TIG weld joint of F82H exhibited low irradiation hardening in a tensile test, compared to the base metal. Microhardness tests and microstructure observation on the neutron-irradiated TIG weld joint of F82H revealed that the over-tempered zone in the heat-affected zone (HAZ) exhibited this good performance. The region in the HAZ where the prior austenite grain size became very fine during welding also exhibited lower irradiation hardening. Hypotheses for these low-hardening mechanisms were proposed based on the phase diagram and grain size.

The Effect of Oxygen on the Corrosion of Vanadium and V-20% Ti by Liquid Lithium

Nuclear Technology

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Nuclear Technology

Heat Treatment of Cr—1 Mo Steel for Breeder Reactor Steam Generators

Nuclear Technology

The Creep-Rupture Properties of a Weld-Overlaid Type 304 Stainless-Steel Forging

Nuclear Technology

Mathematical description for the stress-strain behavior of annealed 2Â¹/â Cr1 Mo steel

We have conducted a detailed series of tensile tests on one heat of annealed 2Â¹/â Cr-1 Mo steel ... more We have conducted a detailed series of tensile tests on one heat of annealed 2Â¹/â Cr-1 Mo steel over the range 25 to 593Â°C (75 to 1100Â°F) and at nominal strain rates of 0.4, 0.04, 0.004, and 0.0004/min. To determine an empirical relationship to represent the flow behavior, we fitted the true-stress true-strain data from these tests to several proposed

Elevated-temperature tensile strength and microstructure of a weld-overlaid type 304 stainless steel forging

Carbon effects on the microstructure and tensile properties of 2 1/4 Cr1 Mo steel weldments

Microstructure and tensile properties of 2 1/4 Cr1 Mo steel weldments with varying carbon contents

Welded test specimens of 2Â¹/â Cr-1 Mo steel were made by joining Â¹/â in. thick plates by the ga... more Welded test specimens of 2Â¹/â Cr-1 Mo steel were made by joining Â¹/â in. thick plates by the gas tungsten-arc process. Microstructure, macrostructure, room temperature hardness, and tensile properties were determined on weld metal, transverse weld specimens and normalized-and-tempered base metal for three laboratory heats of 2Â¹/â Cr-1 Mo steel with 0.003, 0.035, and 0.11 percent C. Welds were made

Miniature tensile test specimens for fusion reactor irradiation studies

Nuclear Engineering and Design. Fusion, 1985

Three miniature sheet-type tensile specimens and a miniature rod-tensile specimen are being used ... more Three miniature sheet-type tensile specimens and a miniature rod-tensile specimen are being used in irradiation-damage studies for fusion reactor materials. Miniature specimens are also being used to determine design properties of irradiated materials. Consequently, a comparison of the tensile properties determined with these different specimens was made by testing cold-worked and solution-annealed Type 316 stainless steel sheet and rod at room temperature, 300°C and 600°C. Good agreement was observed when the properties obtained with the different specimens were compared, and all of the specimens can be used for irradiation-damage studies. However, there were small differences in the properties obtained using the different specimens, and it was recommended that before any miniature specimens are used to determine design-type properties, further studies be conducted.

format_quoteCold-worked rod specimens showed increased strength, with SS-3 specimens having the highest yield and ultimate tensile strength among sheet specimens.format_quote

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Impact behavior of Cr-W steels

Journal of Materials Engineering, 1989

Chromium-molybdenum ferritic (martensitic) steels are leading candidates for the structural compo... more Chromium-molybdenum ferritic (martensitic) steels are leading candidates for the structural components for fusion reactors. However, irradiation of steels containing molybdenum or niobium in a fusion environment will produce long-lived radioactive isotopes that will lead to difficult waste disposal problems. To alleviate the waste disposal problem, ferritic steels are being developed that are analogous to conventional Cr-Mo steels, but with molybdenum

Effect of heat treatment and irradiation temperature on impact behavior of irradiated reduced-activation ferritic steels

Heat-to-heat variation of tensile properties of annealed 2 1/4 Cr-1 Mo steel

Low-chromium reduced-activation chromium-tungsten steels

Tensile and Charpy Impact Properties of Irradiated Reduced Activation Ferritic Steels

Effects of Radiation on Materials: 18th International Symposium, 1999

Tensile tests were conducted on eight reduced-activation Cr-W steels after irradiation to 15-17 a... more Tensile tests were conducted on eight reduced-activation Cr-W steels after irradiation to 15-17 and 26-29 dpa, and Charpy impact tests were conducted on the steels irradiated to 26-29 dpa. Irradiation was in the Fast Flux Test Facility at 365°C on steels containing 2.25-12% Cr, varying amounts of W, V, and Ta, and O.l%C. Previously, tensile specimens were irradiated to 6-8 dpa and Charpy specimens to 6-8, 15-17, and 20-24 dpa. Tensile and Charpy specimens were also thermally aged to 20000 h at 365°C. Thermal aging had little effect on the tensile behavior or the ductile-brittle transition temperature (DBTT), but several steels showed a slight increase in the upper-shelf energy (USE). After =7 dpa, the strength of the steels increased (hardened) and then remained relatively unchanged through 26-29 dpa (Le., the strength saturated with fluence). Postirradiation Charpy impact tests after 26-29 dpa showed that the loss of impact toughness, as measured by an increase in DBTT and a decrease in the USE, remained relatively unchanged from the values after 20-24 dpa, which had been relatively unchanged from the earlier irradiations. As before, the two 9Cr steels had the most irradiation resistance.

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