Author: R. CarbonneauPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
A proposal for an irradiation to compare argon and air-filled zircaloy-4 clad fuel elements in the universal irradiation facility (uif) of the x-6 loop
Author: R. CarbonneauA proposal for the irradiation of zircaloy-4 clad, uo2 fuel elements at post-dryout sheath temperatures in the 625-675 degrees c range in the x-4 loop
Author: V. J. LangmanA proposal for an irradiation to compare helium abd xenon filled zircaloy-2 clad fuel elements in the x6 loop NRX.
Author: J. B. AinscoughThe irradiation of helium and xenon filled zircaloy-2 clad fuel elements in the x6 loop NRX - a proposal for ie 265/x638 : fuel with large pellet/can gaps
Author: J. B. AinscoughA ukaea irradiation to compare helium and xenon filled fuel elements clad in 0.25 mm thick zircaloy-2 in the x-6 loop
Author: D. BramwellPre-irradiation data report on the fabrication of zircaloy-2 clad fuel elements for irradiation in the x-6 loop
Author: R. A. HaywoodPre-irradiation data report on fabrication of zircaloy-2 and zirconium-2.5 percent niobium clad fuel elements for irradiation in the x-6 loop
Author: G. K. WongProposal for the irradiation of zircaloy clad, uo2 fuel elements fabricated by cold swaging
Author: G. H. ChalderA ukaea irradiation of helium and xenon filled zircaloy-2 clad fuel elements in the x6 loop NRX.
Author: D. BramwellGEH-4-63, 64
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 15
Book Description
A brazed end closure is currently being used on prototypical NPR fuel elements. The production closure will use a braze alloy composed of 5% Be + 95% Zry-2 to braze the Zircaloy-2 cap to the jacket and to the metallic uranium core. A similar MTR test, a GEH-4-57, 58, used a braze alloy of the composition 4% Be + 12% Fe + 84% Zry-2 which melts at a lower temperature. In this previous test, element GEH-4-57 failed through a cladding defect located at the base of the braze heat affected zone. Because of this failure it would be desirable to subject a fuel element, which had been subjected to more severe brazing conditions, to the same conditions as GEH-4-57, 58. For this reason the thermal conditions of this test essentially match those of GEH-4-57, 58. This irradiation test consists of two identical fuel elements. The fuel material is normal metallic uranium, Zircaloy-2 clad of the tubular geometry, NPR inner size. The fuel was coextruded at Hanford by General Electric's Fuels Preparation Department. Each element is 10.8 inches in length with flat Zircaloy-2 end caps brazed to the jacket and uranium core with the 5 Be + 95 Zry-2 brazing alloy, then TIG welded to further insure closure integrity. The elements ar 1.254 inches OD and 0.439 inches ID. For hydraulic purposes a 0.343 inch diamater flow restrictor has been fitted into the central flow channel of both elements.