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Papers by Jerry Straalsund

Research paper thumbnail of Comminuting irradiated ferritic steel

OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information), 1985

Research paper thumbnail of Flow duct for nuclear reactors

OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information), 1978

Research paper thumbnail of Harnessing the Hydroelectric Potential of Engineered Drops

Research paper thumbnail of Authors

Research paper thumbnail of Flow duct for nuclear reactors

OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information), 1978

Research paper thumbnail of Fast-Reactor Radiation-Induced Changes in Cladding and Structural Materials

Research paper thumbnail of Effect of Minor Alloy Variations on the Thermal Densification of Austenitic Stainless Steels

Nuclear Technology

Increasing the carbon content of AISI Type-316 stainless steel can produce density changes >0.... more Increasing the carbon content of AISI Type-316 stainless steel can produce density changes >0.1% after aging at 1500 deg F for 100 h. Large additions of phosphorus (0.04 wt%), boron (0.006 wt%), and nitrogen (0.13 wt%) produce no significant density change upon aging. It was concluded that the thermal densification phenomenon observed in austenitic stainless steels is due to the formation of carbides and is linear with the carbon content of the alloy. (auth)

Research paper thumbnail of Irradiation-produced defects in austenitic stainless steel

The microstructure of annealed AISI Type 304 and type 316 stainless steels has been characterized... more The microstructure of annealed AISI Type 304 and type 316 stainless steels has been characterized by transmission electron microscopy as a function of fast reactor irradiation at fluence levels from 4×1021 to 7×1022 n per sq cm (E>0.1 mev) and at irradiation temperatures from 370° to 700°C. Several irradiation produced defect types where found: voids, Frank faulted loops, perfect loops, dislocation networks, and precipitates. Void number density obeys a power law relationship to fluence, wherein the exponent increases with increasing temperature from 0.8 to 1.4 over the irradiation temperatures investigated. The void size is nearly independent of fluence and increases with increasing temperature. The upper limit irradiation temperature for void formation is about 650° to 700°C. The density and size of Frank faulted loops followed trends similar to those found for voids to temperatures of ∼550°C where unfaulted loops, perfect loops, and dislocation networks coexist. These experime...

Research paper thumbnail of Characterization of FTR fuel duct tubes

Research paper thumbnail of Effect of Chemistry Variations on the Recrystallization Temperature of 20 Percent Cold Worked Type 316 Stainless Steel

Research paper thumbnail of Harnessing the Hydroelectric Potential of Engineered Drops

Research paper thumbnail of Experimental Evaluation of Advanced Archimedes Hydrodynamic Screw Geometries

Journal of Hydraulic Engineering

AbstractThere is increasing interest in the application of Archimedes hydrodynamic screws (AHS) t... more AbstractThere is increasing interest in the application of Archimedes hydrodynamic screws (AHS) to generate hydroelectric power. Although numerous theoretical and experimental investigations have b...

Research paper thumbnail of Spatial dependence of void growth rates in the irradiation of thin foils--theory and calculations

Research paper thumbnail of Computer Calculations of Growth Rates of Voids in Stainless Steel During Neutron Irradiation

Research paper thumbnail of The Effect of Chemistry Variations on the Recrystallization Temperature of 20% Cold-Worked Type 316 Stainless Steel

Research paper thumbnail of Effect of Neutron Irradiation on the Elastic Constants of Type-304 Stainless Steel

Nuclear Technology

An ultrasonic technique was used to determine elastic moduli of Type-304 ; stainless-steel sample... more An ultrasonic technique was used to determine elastic moduli of Type-304 ; stainless-steel samples irradiated to fluences as high as 7.5 x 10/suip 22/ n/cm/; sup 2/ (E> 0.1 MeV). Significant decreases in the elastic moduli were found, ; which correlate linearly with irradiation-induced swelling. The Young's modulus ; was found to decrease~2.4%~ per 1% swelling. (auth);

Research paper thumbnail of An Analysis of the Effects of Hydrostatic Stress on Swelling

Research paper thumbnail of Materials Development for Fast Breeder Reactor Cores

Nuclear Technology

A nationally coordinated materials development program for fast breeder reactors is being conduct... more A nationally coordinated materials development program for fast breeder reactors is being conducted to improve the economy and reliability of replaceable core components. The program is comprised of three parallel paths, including reference alloys for present applications, second-generation alloys for near-term applications, and third-generation alloys for longer term applications. Reference alloy work is complete, with the major program emphasis being placed on qualification of titanium-modified Type 316 stainless steel (D9) for core applications. Ferritic alloy, HT-9, has been identified as an excellent duct material, and qualification of this alloy is being phased in as D9 work is completed. Another four alloys have been identified as potential cladding materials and are scheduled for completed development and application by 1988.

Research paper thumbnail of Authors

Research paper thumbnail of Effect of Neutron Irradiation on the Elastic Constants of Type-304 Stainless Steel

Nuclear Technology

An ultrasonic technique was used to determine elastic moduli of Type-304 ; stainless-steel sample... more An ultrasonic technique was used to determine elastic moduli of Type-304 ; stainless-steel samples irradiated to fluences as high as 7.5 x 10/suip 22/ n/cm/; sup 2/ (E> 0.1 MeV). Significant decreases in the elastic moduli were found, ; which correlate linearly with irradiation-induced swelling. The Young's modulus ; was found to decrease~2.4%~ per 1% swelling. (auth);

Research paper thumbnail of Comminuting irradiated ferritic steel

OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information), 1985

Research paper thumbnail of Flow duct for nuclear reactors

OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information), 1978

Research paper thumbnail of Harnessing the Hydroelectric Potential of Engineered Drops

Research paper thumbnail of Authors

Research paper thumbnail of Flow duct for nuclear reactors

OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information), 1978

Research paper thumbnail of Fast-Reactor Radiation-Induced Changes in Cladding and Structural Materials

Research paper thumbnail of Effect of Minor Alloy Variations on the Thermal Densification of Austenitic Stainless Steels

Nuclear Technology

Increasing the carbon content of AISI Type-316 stainless steel can produce density changes >0.... more Increasing the carbon content of AISI Type-316 stainless steel can produce density changes >0.1% after aging at 1500 deg F for 100 h. Large additions of phosphorus (0.04 wt%), boron (0.006 wt%), and nitrogen (0.13 wt%) produce no significant density change upon aging. It was concluded that the thermal densification phenomenon observed in austenitic stainless steels is due to the formation of carbides and is linear with the carbon content of the alloy. (auth)

Research paper thumbnail of Irradiation-produced defects in austenitic stainless steel

The microstructure of annealed AISI Type 304 and type 316 stainless steels has been characterized... more The microstructure of annealed AISI Type 304 and type 316 stainless steels has been characterized by transmission electron microscopy as a function of fast reactor irradiation at fluence levels from 4×1021 to 7×1022 n per sq cm (E>0.1 mev) and at irradiation temperatures from 370° to 700°C. Several irradiation produced defect types where found: voids, Frank faulted loops, perfect loops, dislocation networks, and precipitates. Void number density obeys a power law relationship to fluence, wherein the exponent increases with increasing temperature from 0.8 to 1.4 over the irradiation temperatures investigated. The void size is nearly independent of fluence and increases with increasing temperature. The upper limit irradiation temperature for void formation is about 650° to 700°C. The density and size of Frank faulted loops followed trends similar to those found for voids to temperatures of ∼550°C where unfaulted loops, perfect loops, and dislocation networks coexist. These experime...

Research paper thumbnail of Characterization of FTR fuel duct tubes

Research paper thumbnail of Effect of Chemistry Variations on the Recrystallization Temperature of 20 Percent Cold Worked Type 316 Stainless Steel

Research paper thumbnail of Harnessing the Hydroelectric Potential of Engineered Drops

Research paper thumbnail of Experimental Evaluation of Advanced Archimedes Hydrodynamic Screw Geometries

Journal of Hydraulic Engineering

AbstractThere is increasing interest in the application of Archimedes hydrodynamic screws (AHS) t... more AbstractThere is increasing interest in the application of Archimedes hydrodynamic screws (AHS) to generate hydroelectric power. Although numerous theoretical and experimental investigations have b...

Research paper thumbnail of Spatial dependence of void growth rates in the irradiation of thin foils--theory and calculations

Research paper thumbnail of Computer Calculations of Growth Rates of Voids in Stainless Steel During Neutron Irradiation

Research paper thumbnail of The Effect of Chemistry Variations on the Recrystallization Temperature of 20% Cold-Worked Type 316 Stainless Steel

Research paper thumbnail of Effect of Neutron Irradiation on the Elastic Constants of Type-304 Stainless Steel

Nuclear Technology

An ultrasonic technique was used to determine elastic moduli of Type-304 ; stainless-steel sample... more An ultrasonic technique was used to determine elastic moduli of Type-304 ; stainless-steel samples irradiated to fluences as high as 7.5 x 10/suip 22/ n/cm/; sup 2/ (E> 0.1 MeV). Significant decreases in the elastic moduli were found, ; which correlate linearly with irradiation-induced swelling. The Young's modulus ; was found to decrease~2.4%~ per 1% swelling. (auth);

Research paper thumbnail of An Analysis of the Effects of Hydrostatic Stress on Swelling

Research paper thumbnail of Materials Development for Fast Breeder Reactor Cores

Nuclear Technology

A nationally coordinated materials development program for fast breeder reactors is being conduct... more A nationally coordinated materials development program for fast breeder reactors is being conducted to improve the economy and reliability of replaceable core components. The program is comprised of three parallel paths, including reference alloys for present applications, second-generation alloys for near-term applications, and third-generation alloys for longer term applications. Reference alloy work is complete, with the major program emphasis being placed on qualification of titanium-modified Type 316 stainless steel (D9) for core applications. Ferritic alloy, HT-9, has been identified as an excellent duct material, and qualification of this alloy is being phased in as D9 work is completed. Another four alloys have been identified as potential cladding materials and are scheduled for completed development and application by 1988.

Research paper thumbnail of Authors

Research paper thumbnail of Effect of Neutron Irradiation on the Elastic Constants of Type-304 Stainless Steel

Nuclear Technology

An ultrasonic technique was used to determine elastic moduli of Type-304 ; stainless-steel sample... more An ultrasonic technique was used to determine elastic moduli of Type-304 ; stainless-steel samples irradiated to fluences as high as 7.5 x 10/suip 22/ n/cm/; sup 2/ (E> 0.1 MeV). Significant decreases in the elastic moduli were found, ; which correlate linearly with irradiation-induced swelling. The Young's modulus ; was found to decrease~2.4%~ per 1% swelling. (auth);

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