The Creep ductility in-reactor of cold worked zr-2.5 wt percent nb pressure tubes

The Creep ductility in-reactor of cold worked zr-2.5 wt percent nb pressure tubes PDF Author: C. E. Ells
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Category :
Languages : en
Pages : 0

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The Creep ductility in-reactor of cold worked zr-2.5 wt percent nb pressure tubes

The Creep ductility in-reactor of cold worked zr-2.5 wt percent nb pressure tubes PDF Author: C. E. Ells
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

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Creep ductility of cold-worked zr-2.5wt percent nb and zircaloy-2 tubes in-reactor

Creep ductility of cold-worked zr-2.5wt percent nb and zircaloy-2 tubes in-reactor PDF Author: E. F. Ibrahim
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Category :
Languages : en
Pages : 0

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A proposal to measure the in-reactor Creep rate of cold-worked zr-2.5 wt percent nb under low compressive stress at 573 k (300 degrees c). (test rx-55).

A proposal to measure the in-reactor Creep rate of cold-worked zr-2.5 wt percent nb under low compressive stress at 573 k (300 degrees c). (test rx-55). PDF Author: C. J. Simpson
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ISBN:
Category :
Languages : en
Pages : 0

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In-reactor Deformation of a Pilgered Cold-worked ZR-2.5 Wt Percent NB Pressure Tube

In-reactor Deformation of a Pilgered Cold-worked ZR-2.5 Wt Percent NB Pressure Tube PDF Author: Atomic Energy of Canada Limited
Publisher:
ISBN:
Category :
Languages : en
Pages :

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A proposal to measure the in-reactor Creep rate of cold-worked zr-2.5 wt percent nb under low tensile stresses at 573 k (300 degrees c). (test rx-54).

A proposal to measure the in-reactor Creep rate of cold-worked zr-2.5 wt percent nb under low tensile stresses at 573 k (300 degrees c). (test rx-54). PDF Author: C. J. Simpson
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

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Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
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ISBN:
Category : Nuclear energy
Languages : en
Pages : 1110

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Temperature and Neutron Flux Dependence of In-Reactor Creep for Cold-Worked Zr-2.5Nb

Temperature and Neutron Flux Dependence of In-Reactor Creep for Cold-Worked Zr-2.5Nb PDF Author: Robert F. DeAbreu
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ISBN:
Category : Nuclear activation analysis
Languages : en
Pages : 27

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Over the past 10 years, internally pressurized capsules made from Zr-2.5Nb tubing have been irradiated in the National Research Universal (NRU) reactor at Chalk River Laboratories at temperatures of 280, 320, and 340°C and dose rates between 3 x 1015 n . m-2 . s-1 and 2 x 1017 n . m-2 . s-1 (E > 1 MeV). Periodic gaging has been used to assess the primary and secondary (steady-state) creep behavior. The objective of this detailed and controlled experiment was to determine, for the first time, the creep and microstructure evolution in Zr-2.5Nb tubing over a wide range of irradiation conditions for fast neutron fluxes applicable to a CANDU pressure tube. Similar but "accelerated" creep experiments have been conducted in the Osiris test reactor at fast neutron fluxes of approximately 1.8 x 1018 n . m-2 . s-1 (E > 1 MeV), much greater than the neutron fluxes in the NRU reactor. Although accelerated tests in high-flux reactors such as Osiris provide information on irradiation creep, they do not represent the neutron flux conditions applicable to a power reactor. Tests covering power reactor operating conditions are needed to develop models for in-reactor creep of pressure tubes under the appropriate conditions. The data from the NRU reactor are compared with results from creep capsules with similar starting microstructures but irradiated in the Osiris reactor. The results show that the steady-state diametral and axial creep rates have a complex dependence on stress, temperature, and fast neutron flux. Data from out-reactor creep tests on unirradiated and pre-irradiated creep capsules that show the effect of prior irradiation on creep are also reported. The results are discussed in terms of a combination of creep mechanisms involving dislocation glide and mass transport.

Design equation for deformation of cold-worked zr-2.5 percent nb pressure tubes in-reactor

Design equation for deformation of cold-worked zr-2.5 percent nb pressure tubes in-reactor PDF Author: E. F. Ibrahim
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ISBN:
Category :
Languages : en
Pages : 0

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In-Reactor Creep of Cold-Worked Zircaloy-2 and Zirconium- 2.5 Wt Percent Niobium Pressure Tubes

In-Reactor Creep of Cold-Worked Zircaloy-2 and Zirconium- 2.5 Wt Percent Niobium Pressure Tubes PDF Author: Atomic Energy of Canada Limited
Publisher:
ISBN:
Category :
Languages : en
Pages : 35

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Irradiation-enhanced Creep of Cold-worked Zr-2.5Nb Tubes and Helical-springs

Irradiation-enhanced Creep of Cold-worked Zr-2.5Nb Tubes and Helical-springs PDF Author: A. R. Causey
Publisher: Chalk River, Ont. : Reactor Materials Research Branch, Chalk River Laboratories
ISBN:
Category : Anisotropy
Languages : en
Pages : 34

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This report investigates the anistrophy of irradiation-enhanced creep of cold-worked Zr-2.5Nb at 548-563 K using internally-pressurized capsules and axially loaded helical-springs. The test specimens were machined from small diameter extruded and cold-worked tubing that had crystallographic texture and microstructure similar to that of CANDU power reactor pressure tubes. The biaxial creep capsules and the helical-springs were irradiated for 9,525 and 16,670 hours, respectively, in a fast neutron flux.