Author: J. F. WalkerPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
A proposal for the irradiation of uranium metal alloys
Author: J. F. WalkerProposal for the irradiation of plutonium-aluminum and uranium-silicon alloys in x-2 loop, NRX, September 1957 - January 1958
Author: T. I. JonesIrradiation Swelling of Uranium and Uranium Alloys
Author: Gordon G. BentlePublisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 76
Book Description
A proposal for comparing the irradiation growth of calder uranium, uranium - 1/2 at.percent chromium alloy and uranium - 3 at .percent molybdenum alloy in NRX.
Author: A proposal for comparing the irradiation growth of clader uranium- u-1/2 at .percent chromium alloy and uranium - 3 at .percent molybdenum alloy in NRX.
Author: W. N. MillerA proposal for comparing the irradiation growth of clader uranum, uranium-1/2 at .percent chromium alloy and uranium - 3 at .percent molybdenum alloy in NRX.
Author: D. L. WardIrradiation of U-Mo Base Alloys
Author: M. P. JohnsonPublisher:
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
Irradiation Behavior of Uranium-fissium Alloys. EBR-II Project
Author: J. H. KittelPublisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 46
Book Description
A series of uranium-fissium and uranium-fissium-zirconium alloys was irradiated in thermal test reactors to study the relationship of dimensional stability to alloy composition, thermal cycling, burnup, irradiation temperature, post-irradiation heating, and cladding restraint. None of the alloy compositions tested showed irradiation behavior superior to the uranium-5 wt./% fissium alloy that has been used as driver fuel in EBR-II since it began operation. This alloy is among those uranium-base alloys most capable of resisting high-temperature irradiation swelling. None of the alloys showed evidence of the reversion to the metastable gamma phase that has been observed in comparable uranium-molybdenum alloys. Swelling of uranium-fissium alloys was effectively restrained by most of the 0.009-inch thick cladding materials investigated. Local hydrostatic forces due to swelling of the fuel caused the fuel to extrude extensively out of small vent holes in the cladding. Little axial fuel movement occurred within the cladding, however, even when the upper fuel surface was entirely unrestrained.
Irradiation Stability of Uranium Alloys at High Exposures
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 5
Book Description
Postirradiation examinations were begun of a series of unrestrained dilute uranium alloy specimens irradiated to exposures up to 13,000 MWD/T in NaK-containing stainless steel capsules. This test, part of a program of development of uranium metal fuels for desalination and power reactors sponsored by the Division of Reactor Development and Technology, has the objective of defining the temperature and exposure limits of swelling resistance of the alloyed uranium. This paper discusses those test results.
Electrorefining of Irradiated Thorium-uranium Alloy
Author: W. N. HansenPublisher:
ISBN:
Category : Thorium alloys
Languages : en
Pages : 40
Book Description