High-fluence irradiation growth of cold-worked zr-2.5nb PDF Download
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Author: R. A. Holt
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Book Description
Author: R. A. Holt
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Author: RA. Holt
Publisher:
ISBN:
Category : Iron
Languages : en
Pages : 19
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Book Description
Irradiation growth specimens manufactured from cold-worked Zr-2.5Nb pressure tube material have been irradiated in Osiris at a fast flux of ~1.8 x 1018 n . m-2 . s-1E > 1 MeV, at nominal temperatures of 553 and 583 K, to growth strains of 1%. The pressure tubes have a pronounced crystallographic texture, with ~95% of the basal plane normals in the radial/transverse plane, predominantly in the transverse direction. Both longitudinal specimens, which generally exhibit positive growth strains, and transverse specimens, which generally exhibit negative strains with approximately 50% of the magnitude of the axial strains, show nonlinear growth, the rate increasing gradually with fluence up to 1.3 x 1026 n . m-2, E > 1 MeV (580 K) and 1.7 x 1026 n . m-2, E > 1 MeV (550 K).
Author: RA. Holt
Publisher:
ISBN:
Category : Dislocation density
Languages : en
Pages : 16
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Book Description
Specimens of cold-worked Zr-2.5% Nb pressure tube material fabricated by several different routes have been irradiated unstressed in the Dido reactor at Atomic Energy Research Establishment (AERE) Harwell to fluences up to 7.5 x 1025 n/m2, E & 1 MeV (about 18 dpa). Their irradiation growth behavior has been investigated as a function of temperature in the range 553 to 623 K.
Author:
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 849
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Book Description
Author: Leo F. P. Van Swam
Publisher: ASTM International
ISBN: 0803111991
Category : Nuclear fuel claddings
Languages : en
Pages : 781
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Book Description
Author: RA. Holt
Publisher:
ISBN:
Category : Congress
Languages : en
Pages : 15
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Book Description
Accelerating irradiation growth has been reported for several zirconium alloys with a range of metallurgical states during high-temperature tests in fast-breeder reactors (673 to 723 K) for annealed Zircaloys in thermal test reactors at power reactor temperatures (523 to 623 K) and in power reactor core components fabricated from annealed or recrystallized Zircaloy. In the latter case, there was a transition from low to high irradiation growth rates at moderate fluences (about 3 x 1025 n/m2, E > 1 MeV, at 580 K) related to the nucleation and growth of basal plane c-component loops.
Author: RB. Adamson
Publisher:
ISBN:
Category : Annealed
Languages : en
Pages : 27
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Book Description
Irradiation growth behavior of Zircaloy-2 and -4 was studied on specimens irradiated in the Experimental Breeder Reactor II to fluences of 1.4 to 6.3 x 1025 neutrons (n).m-2 (E > 1 MeV) in the temperature range 644 to 723 K. Measurements in the three principal directions on annealed and cold-worked/stress-relieved Zircaloy-2 slab materials provided evidence that growth is a constant-volume process up to about 680 K. The growth strains were shown to be determined by the crystallographic texture, that is, proportional to (1-3(1-3fdc)), where), where fdc is the fraction of basal poles, is the fraction of basal poles, fc, in the direction d. The growth strains for annealed and cold-worked Zircaloy were large relative to previously reported data, were similar in magnitude, were strongly dependent on irradiation temperature, and varied linearly with fluence over the range investigated. Transmission electron microscopy on annealed Zircaloy-4 specimens revealed a few small voids and larger cavities, a grain boundary second phase, and dislocation loops, tangles, and arrays. The high growth strains in annealed Zircaloy appear to be governed by dislocation arrays formed during irradiation. This implies a change in growth mechanism from that pertaining at lower temperatures in annealed material. The data suggest a transition from saturating steady-state growth at lower temperatures to increasing and eventually high steady-state rates under the conditions of these tests.
Author: R. P. Tucker
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Author: R. A. Murgatroyd
Publisher:
ISBN:
Category :
Languages : en
Pages : 10
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Book Description
Author: RB. Adamson
Publisher:
ISBN:
Category : Heat treatment
Languages : en
Pages : 18
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Book Description
Data on irradiation growth of Zircaloy is presented. Irradiation growth is defined as irradiation-induced changes in dimensions in the absence of an applied stress. It is shown that the primary variables are fluence, irradiation temperature, amount of prior cold work, heat treatment, and texture. For recrystallized Zircaloy: growth (a) increases as f, the fraction of basal poles in measurement direction, decreases; shrinkage is possible for large f-factors, (b) increases with increasing temperature up to about 300°C, above which it decreases, (c) tends towards saturation for fluences greater than about 1 x 1021 neutrons (n)/cm2(E> 1 MeV). For cold worked/ stress relieved material: growth (a) increases linearly with fluence up to at least 3 x 1021 n/cm2, and (b) increases linearly with increase in the amount of cold work. For recrystallized material, all irradiation growth is recovered during suitable thermal anneals, while for cold worked material only a portion of the growth is recoverable. Rapid recovery occurs above 350°C (644°F) with an activation energy of 1.67 eV. Mechanistic implications of the gathered data are discussed.
