scholarly journals REPAIR OF CASTING FLAWS IN AN EIGHT INCH STAINLESS STEEL CHECK VALVE AT THE PLUTONIUM RECYCLE TEST REACTOR.

1969 ◽  
Author(s):  
R.H. Purcell
Keyword(s):  
Stainless Steel ◽  
Check Valve ◽  
Test Reactor

Design and Fabrication of the Piezoelectrically Actuated Micropump with Implanted Check Valves

2013 ◽  
Vol 284-287 ◽  
pp. 2032-2036
Author(s):  
Chiang Ho Cheng ◽  
Yi Pin Tseng
Keyword(s):  
Stainless Steel ◽  
Flow Rate ◽  
Steel Substrate ◽  
Check Valve ◽  
Maximum Flow ◽  
Mems Fabrication ◽  
Sinusoidal Waveform ◽  
Nickel Electroforming ◽  
Bridge Type ◽  
Type Check

This paper aims to present the design, fabrication and test of a novel piezoelectrically actuated, check valve embedded micropump having the advantages of miniature size, light weight and low power consumption. The micropump consists of a piezoelectric actuator, a stainless steel chamber layer with membrane, two stainless steel channel layers with two valve seats, and a nickel check valve layer with two bridge-type check valves. The check valve layer was fabricated by nickel electroforming process on a stainless steel substrate. The chamber and the channel layer were made of the stainless steel manufactured using the lithography and etching process based on MEMS fabrication technology. The effects of check valve thickness, operating frequency and back pressure on the flow rate of the micropump are investigated. The micropump with check valve 20 μm in thickness obtained higher output values under the sinusoidal waveform of 120 Vpp and 160 Hz. The maximum flow rate and backpressure are 1.82 ml/min and 32 kPa, respectively.

Light element analysis of irradiation-induced precipitates in Ti-modified 316 stainless steel

1983 ◽  
Vol 41 ◽  
pp. 384-385
Author(s):  
L. E. Thomas
Keyword(s):  
Stainless Steel ◽  
Light Element ◽  
Steel Specimen ◽  
Scanning Transmission Electron Microscope ◽  
Nominal Composition ◽  
Element Analysis ◽  
316 Stainless Steel ◽  
Transmission Electron ◽  
Scanning Transmission ◽  
Test Reactor

G and n phases are complex nickel silicides which commonly form in Fe-Ni-Cr based stainless steels and superalloys during neutron irradiation at 400-600°C. Both phases are cubic and are structurally similar to the common carbides M2 3C6 and M6C which form in many of the same alloys during thermal aging. Although G and n have been analyzed previously by energy-dispersive x-ray spectrometry (EDXS), little is known about their carbon contents.To further determine the compositional relationships between the G/n silicides and the M 23C 6/M6C carbides, an irradiated Ti-modified 316 stainless steel specimen containing 0.05 to 0.5μm particles of G and n was analyzed by means of electron energy loss spectroscopy (ELS) and EDXS in a field emission gun scanning transmission electron microscope (STEM). The alloy, LSI, has the nominal composition of Fe-16.8Cr-13.5Ni-l.9Mo-0.87Si-2.0Mn-.15Ti-.045C and was irradiated to 2 x 1022n/cm2, E >0.1 MeV, at 510°C in the EBR-II breeder test reactor.

Cylindricity Sensitivity Thermal Model of the AGR-5/6/7 Experiment in the Advanced Test Reactor

2020 ◽  
Author(s):  
Grant L. Hawkes
Keyword(s):  
Heat Transfer ◽  
Stainless Steel ◽  
Thermal Model ◽  
National Laboratory ◽  
Sensitivity Study ◽  
Operating Conditions ◽  
Department Of Energy ◽  
Easy Method ◽  
Gas Gap ◽  
Test Reactor

Abstract The AGR-5/6/7 experiment is currently being irradiated in the Advanced Test Reactor (ATR) at the Idaho National Laboratory and is approximately 70% complete. Several fuel and material irradiation experiments have been planned for the U.S. Department of Energy Advanced Gas Reactor Fuel Development and Qualification Program, which supports the development and qualification of tristructural isotropic (TRISO)-coated particle fuel for use in high-temperature gas-cooled reactors. The goals of these experiments are to provide irradiation performance data to support fuel process development, qualify fuel for normal operating conditions, support development of fuel performance models and codes, and provide irradiated fuel and materials for post-irradiation examination and safety testing. Originally planned and named as separate fuel experiments, but subsequently combined into a single test train, AGR-5/6/7 is testing low-enriched uranium oxycarbide TRISO fuel. The AGR-5/6/7 test train has five capsules with thermocouples and independent gas control mixtures. Unique to this paper is a sensitivity study concerning the cylindricity of the graphite holders containing the fuel compacts and their eccentricity in relation to the stainless-steel capsule walls. Each capsule has small nubs on the outside used for centering the graphite holder inside the stainless-steel capsule with a small gas gap used to control temperature. Due to machining tolerances of these nubs, and vibration wearing the nubs down when the experiment is running in the reactor, the possibility exists that the holder may move around radially. Each capsule is equipped with several thermocouples placed at various radii and depths within each graphite holder. This paper will show the sensitivity of offsetting the graphite holder for various radii in 45-degree increments around the circle with the objective of minimizing the difference between the measured thermocouples and the modeled thermocouple temperatures. Separate gas mixtures of helium/neon are introduced into this gas gap between the holder and capsule wall and changed as necessary to maintain the desired thermocouple temperatures to keep the fuel compacts at a constant temperature as the nuclear reactor conditions change. The goal of the sensitivity study is to find a radius and an angle to offset the holder from perfectly centered for each of the five capsules separately. The complex thermal model includes fission heating, gamma heating, radiation heat transfer, and heat transfer via conduction and radiation across the control gaps. Subroutines linked to the thermal model offer an easy method to offset the graphite holder from the capsule walls without remeshing the entire model.

Irradiation Testing of Zirconium Alloys and Stainless Steel in Fast Breeder Test Reactor, India

2012 ◽  
pp. 176-191 ◽  
Author(s):  
S. Murugan ◽  
P. V. Kumar ◽  
Jojo Joseph ◽  
S. Venugopal ◽  
T. Jayakumar ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Zirconium Alloys ◽  
Fast Breeder Test Reactor ◽  
Test Reactor

Comparison of Texas Liquid Sampler with Missouri Bottle for Sampling Liquid Fertilizers: Collaborative Study

1993 ◽  
Vol 76 (4) ◽  
pp. 749-753
Author(s):  
George W Latimer ◽  
◽  
J Comstock ◽  
D Dubberly ◽  
T Jessup ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Total Nitrogen ◽  
Collaborative Study ◽  
Check Valve ◽  
Sampling Procedure ◽  
Available Phosphorus ◽  
Liquid Sample ◽  
Polyethylene Tube ◽  
Sampling Tube ◽  
Liquid Sampling

Abstract Six laboratories participated in a collaborative study designed to qualify the Texas liquid sampling tube as a device for sampling liquid fertilizers. The Texas sampler is a polyethylene tube with a stainless steel check valve on one end. The tube, which is threaded so that it can be expanded in length, enables acquisition of a uniform profile across a liquid sample. The 6 collaborators sampled 33 loads of fertilizer, 8 of which were slurries, using both the Texas tube and the Missouri bottle (AOAC 969.01). The resulting subsamples were analyzed for total nitrogen, available phosphorus, and soluble potash. Analysis of the data showed no significant (p < 0.05) difference in results. This sampling procedure, using the Texas liquid sampler, was adopted first action by AOAC International as a suitable means of sampling liquid fertilizers.

Development of a stainless steel check valve for cryogenic applications

Cryogenics ◽  
2007 ◽  
Vol 47 (2) ◽  
pp. 121-126 ◽  
Author(s):  
T.T. Veenstra ◽  
G.C.F. Venhorst ◽  
J.F. Burger ◽  
H.J. Holland ◽  
H.J.M. ter Brake ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Check Valve

scholarly journals The Innovations, Technology and Waste Management Approaches to Safely Package and Transport the World’s First Radioactive Fusion Research Reactor for Burial

2003 ◽  
Author(s):  
Keith Rule ◽  
Erik Perry ◽  
Jim Chrzanowski ◽  
Mike Viola ◽  
Ron Strykowsky
Keyword(s):  
Stainless Steel ◽  
Best Practices ◽  
Radioactive Waste ◽  
Waste Management ◽  
Research Reactor ◽  
Fusion Research ◽  
Disposal Facility ◽  
Management Approaches ◽  
Test Reactor ◽  
The Many

Original estimates stated that the amount of radioactive waste that will be generated during the dismantling of the Tokamak Fusion Test Reactor (Fig. 1) will approach 2 Million Kilograms with an associated volume of 2500 cubic meters. The materials were activated by 14 Mev neutrons and were highly contaminated with tritium, which present unique challenges to maintain integrity during packaging and transportation. In addition, the majority of this material is stainless steel and copper structural metal that were specifically designed and manufactured for this one-of-a-kind fusion research reactor. This provided further complexity in planning and managing the waste. We will discuss the engineering concepts, innovative practices, and technologies that were utilized to size reduce, stabilize and package the many unique and complex components of this reactor. This waste was packaged and shipped in many different configurations and methods according to the transportation regulations and disposal facility requirements. For this particular project we were able to utilize two separate disposal facilities for burial. This paper will conclude with a complete summary of the actual results of the waste management costs, volumes, and best practices that were developed from this groundbreaking and successful project.

NiAl precipitation in Fe-12w/o Cr-5w/o Ni-4w/o Al

1983 ◽  
Vol 41 ◽  
pp. 202-203
Author(s):  
L.E. Murr ◽  
J.S. Dunning ◽  
S. Shankar
Keyword(s):  
Solid Solution ◽  
Stainless Steel ◽  
Stainless Steels ◽  
Alloy Composition ◽  
Chromium Content ◽  
Scale Up ◽  
Optical Metallography ◽  
Property Evaluation ◽  
310 Stainless Steel ◽  
Microstructural Studies

Aluminum additions to conventional 18Cr-8Ni austenitic stainless steel compositions impart excellent resistance to high sulfur environments. However, problems are typically encountered with aluminum additions above about 1% due to embrittlement caused by aluminum in solid solution and the precipitation of NiAl. Consequently, little use has been made of aluminum alloy additions to stainless steels for use in sulfur or H2S environments in the chemical industry, energy conversion or generation, and mineral processing, for example.A research program at the Albany Research Center has concentrated on the development of a wrought alloy composition with as low a chromium content as possible, with the idea of developing a low-chromium substitute for 310 stainless steel (25Cr-20Ni) which is often used in high-sulfur environments. On the basis of workability and microstructural studies involving optical metallography on 100g button ingots soaked at 700°C and air-cooled, a low-alloy composition Fe-12Cr-5Ni-4Al (in wt %) was selected for scale up and property evaluation.

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