Proposal to irradiate curved compact toughness and tensile specimens of cold-worked zr-2.5nb pressure tubes in a thirty-element materials test bundle in the u-1 or u-2 loop of the NRU reactor PDF Download
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Author: J. W. Bowden
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Author: J. W. Bowden
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Category :
Languages : en
Pages : 0
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Author: A. R. Causey
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Category :
Languages : en
Pages : 0
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Author: R. Choubey
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Category : Charpy
Languages : en
Pages : 30
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About 400 pressure-tubes made of cold-worked Zr-2.5Nb are used in a CANDU power reactor to contain the nuclear fuel and the heat transport fluid, heavy water, at between 250 to 310°C at a pressure of about 10 MPa. The fracture toughness of these tubes is needed to determine if they are fit for service. We have measured the fracture toughness by bursting 450 mm long tube sections and using 17 mm curved compact toughness (C(T)) specimens, employing the J-integral resistance curve method in both cases. The burst test is expensive but it simulates the stress state under which the pressure tubes operate, while the small specimen method is more economical although the interpretation of data is more difficult.
Author: CK. (Peter) Chow
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Category : Curved specimens
Languages : en
Pages : 21
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This paper describes a case in which nonstandard test configurations had to be used to assess fracture toughness, and an experimental, analytical program to support the validity of the results.
Author: S. St Lawrence
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Category : Delayed hydride cracking
Languages : en
Pages : 24
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To determine the fracture properties of Zr-2.5Nb pressure tubes irradiated until the end of design life, cantilever beam, curved compact toughness, and transverse tensile samples were prepared from a typical pressure tube and irradiated in the high flux reactor OSIRIS at CEA, Saclay, France. Experiments were conducted on two batches of samples mounted in two irradiation inserts. Each insert held sixteen samples of each type of specimen. The first insert was irradiated to a fluence corresponding to approximately half of the design life in a CANDU3 reactor. The experimental results were reported in [1]. Samples in the second insert were irradiated for 10.5 years in OSIRIS and received a maximum neutron fluence of 2.61 x 1026 n/m2 (E > 1 MeV), being equivalent to 2.98 x 1026 n/m2 (E > 1 MeV) in a CANDU reactor, i.e., corresponding to ~30 years operation in CANDU reactors at 80 % capacity factor. The present report describes the results of tensile, fracture toughness, and Delayed Hydride Cracking (DHC) tests and XRD microstructure analysis from the second batch of specimens. A continuous and gradual evolution in tensile, fracture, DHC properties, and dislocation densities is demonstrated without any evidence of a sudden change following the initial transitient at very low fluence. In the whole high fluence range, there is a very slow rate of increase in c-component dislocation density, strength, and DHC velocity and a slow reduction in elongation and Nb concentration in the ?-phase. The a-type dislocation density and fracture toughness remain approximately constant. The results from the second insert of specimens confirm that, following the initial transient at very low fluence, there is little further change in the fracture properties of Zr-2.5Nb pressure tube material. Therefore, material properties behave in a stable and predicable manner to the end of a 30 years design life for CANDU reactor pressure tubes.
Author: J. M. Smeltzer
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Category :
Languages : en
Pages : 0
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Author: C. K. Chow
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Category :
Languages : en
Pages : 0
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Author: P. H. Davies
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Category :
Languages : en
Pages : 0
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Author: C. K. Chow
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Category :
Languages : en
Pages : 0
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Author: J. J. Schankula
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Category :
Languages : en
Pages : 0
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