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Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
The stress-strain properties of the APDA reference alloy of uranium- 10 wt.% molybdenum at various burnups up to 2.1 total at. % are described. Data were ob tained on both irradiated and unirradiated specimens of the alloy by the use of a remotely operated bend-testing machine. Tensile properties of unirradiated material are also reported for comparison with data obtained from the bend tests. The mathematical procedure used in obtainirg equivalent uniaxial stress-strain properties from the bend-test data is described in the Appendix. The results of the bend tests indicate that the physical properties of the reference alloy were severely affected by irradiation to burnups as high as 2.1 total at.%. At a test temperature of 500 deg C, the modulus of elasticity, ultimate strength, and strain at fracture decreased rapidly up to a burnup of about 0.5 to 1.0 total at.% with the rate of change decreasing thereafter. No important differences were noted between coextruded and hot-rolled material. An indication was obtained that the ultimate strength of the alloy was improved with increasing irradiation temperatures up to about 500 deg C. Data obainined on unirradiated material indicated that ductility of the reference alloy was lower at 500 deg C than at room temperature. Stress-strain curves for the irradiated specimens are included. The value of these data is limited because of the large number of variables encountered in the specimen histories and the small number of tests involved in this program. (auth).
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
The stress-strain properties of the APDA reference alloy of uranium- 10 wt.% molybdenum at various burnups up to 2.1 total at. % are described. Data were ob tained on both irradiated and unirradiated specimens of the alloy by the use of a remotely operated bend-testing machine. Tensile properties of unirradiated material are also reported for comparison with data obtained from the bend tests. The mathematical procedure used in obtainirg equivalent uniaxial stress-strain properties from the bend-test data is described in the Appendix. The results of the bend tests indicate that the physical properties of the reference alloy were severely affected by irradiation to burnups as high as 2.1 total at.%. At a test temperature of 500 deg C, the modulus of elasticity, ultimate strength, and strain at fracture decreased rapidly up to a burnup of about 0.5 to 1.0 total at.% with the rate of change decreasing thereafter. No important differences were noted between coextruded and hot-rolled material. An indication was obtained that the ultimate strength of the alloy was improved with increasing irradiation temperatures up to about 500 deg C. Data obainined on unirradiated material indicated that ductility of the reference alloy was lower at 500 deg C than at room temperature. Stress-strain curves for the irradiated specimens are included. The value of these data is limited because of the large number of variables encountered in the specimen histories and the small number of tests involved in this program. (auth).
Author: Jason L. Schulthess Publisher: ISBN: 9781085583084 Category : Uranium alloys Languages : en Pages : 174
Book Description
Studies were conducted to establish the mechanical properties of uranium 10 wt.% molybdenum (U-10Mo) in both the un-irradiated condition and after neutron irradiation. In the un-irradiated condition, mechanical properties were obtained for various temperatures and after the alloy had been wrought processed by rolling into four different rolling conditions. The irradiated mechanical properties were obtained at various fission densities and then the degradation of the mechanical properties from the un-irradiated to irradiated condition evaluated and a correlation with porosity developed. The mechanical properties obtained of the un-irradiated material differed from that previously published in the literature, which was expected due to the differences in thermomechanical processing conditions between the materials evaluated. The mechanical properties degraded as fission density increased as expected, and correlate to the increase of porosity that develops with increasing fission density.
Author: M. P. Johnson Publisher: ISBN: Category : Molybdenum alloys Languages : en Pages : 38
Book Description
A series of experiments was designed to assess the suitability of uranium-molybdenum alloys as high-temperature, high-burnup fuels for advanced sodium cooled reactors. Specimens with molybdenum contents between 3 and 10% were subjected to capsule irradiation tests in the Materials Testing Reactor, to burnups up to 10,000 Mwd/MTU at temperatures between 800 and 1500 deg F. The results indicated that molybdenum has a considerable effect in reducing the swelling due to irradiation. For example. 3% molybdemum reduces the swelling from 25%, for pure uranium. to 7% at approximates 3,000 Mwd/MTU at 1270 deg F. Further swelling resistance can be gained by increasing the molybdenum content, but the amount gained becomes successively smaller. At higher irradiation levels, the amount of swelling rapidly becomes greater, and larger amounts of molybdenum are required to provide similar resistance. A limit of 7% swelling, at 900 deg F and an irradiation of 7,230 Mwd/ MTU, requires the use of 10% Nonemolybdenum in the alloy. The burnup rates were in the range of 2.0 to 4.0 x 10p13s fissiom/cc-sec. Small ternary additions of silicon and aluminum were shown to have a noticeable effect in reducing swelling when added to a U-3% Mo alloy base. Under the conditions of the present experiment, 0.26% silicon or 0.38% aluminum were equivalent to 1 to 1 1/2% molybdenum. The Advanced Sodium Cooled Reactor requires a fuel capable of being irradiated to 20,000 Mwd/MTU at temperatures up to 1500 deg C in metal fuel, or equivalent in ceramic fuel. It is concluded that even the highest molybdenum contents considered did not produce a fuel capable of operating satisfactorily under these conditions. The alloys would be useful, however, for less exacting conditions. The U-3% Mo alloy is capable of use up to 3,000 Mwd/MTU at temperatures of 1300 deg F before swelling becomes excessive. The addition of silicon and aluminum would increase this limit to at least 3,000 Mwd/MTU, and possibly more if the
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
Tbe true stress--true strain curves and modulus of elasticity were determined on a uranium--10 wt. % molybdenum alloy at room temperature and at 250, 500, were conducted in a liquid bath to minimize oxidation effects. The test results indicated that the strength properties and modulus of elasticity of the uranium-10 wt. % molybdenum alloy decreased with increasing temperature from room temperature to 1250 d F. Up to 500 d F, the true stress values increased with increasing true strain from the start of loading until the specimens failed. At higher temperatures, however, the true stress reached a maximum at an intermediate strain value before rupture, probably because of a tendency of the alloy to creep at a faster rate than the applied rate of strain. (auth).
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
The mechanical and physical properties of U --10 wt.% Mo before and after irradiation have been studied. The pre-irradiation properties and some of the post-irradiation physical properties are presented in graphical and tabular form. (J.S.R.).
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Author: R. E. Hueschen
Author: Jason L. Schulthess
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