Acceleration of Creep and growth of annealed zircaloy-4 by pre-irradiation to high fluences PDF Download
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Author: A. R. Causey
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Book Description
This report presents the final safety analysis for the preparation, conduct, and post-test discharge operation for the full-length high temperature experiment-5 (flht-5) to be conducted in the l-24 position of the national research universal (nru) reactor at chalk river nuclear laboratories (crnl), ontario, canada. the test is sponsored by an international group organized by the u.s. nuclear regulatory commission. the test is designed and conducted by staff from pacific northwest laboratory with crnl staff support. the test will study the consequences of loss-of-coolant and the progression of severe fuel damage. an array of full-length lwr fuel rods will be subjected to conditions that simulate loss-of-coolant flow at decay-heat power level. the 12-position array includes one pre-irradiated pwr rod, 10 fresh fuel rods, and one instrument thimble containing a dummy steel rod. the boilaway of the coolant will permit heatup of the rods to the point of rapid cladding oxidation with concomitant cladding melting, partial fuel liquefaction, fuel oxidation, hydrogen generation, and fission product release. the hydrogen generation (from the oxidation reaction), the bundle temperatures, the liquid level, and the fission product release will be monitored during the test. the melt progression will be assessed using post test visual and metallographic examination results. experience from similar flht tests is combined with analysis results to show that: 1) high-temperature material will be contained within the shroud that surrounds the rod array, precluding damage to the nru loop pressure tube; 2) the released fission products and hydrogen will be contained and disposed of by the effluent control system in a manner that poses no unresolved safety hazard to operating personnel or to the public; and 3) the radiation exposure to operating personnel and to the public will remain below approved control limits.
Author: A. R. Causey
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Book Description
This report presents the final safety analysis for the preparation, conduct, and post-test discharge operation for the full-length high temperature experiment-5 (flht-5) to be conducted in the l-24 position of the national research universal (nru) reactor at chalk river nuclear laboratories (crnl), ontario, canada. the test is sponsored by an international group organized by the u.s. nuclear regulatory commission. the test is designed and conducted by staff from pacific northwest laboratory with crnl staff support. the test will study the consequences of loss-of-coolant and the progression of severe fuel damage. an array of full-length lwr fuel rods will be subjected to conditions that simulate loss-of-coolant flow at decay-heat power level. the 12-position array includes one pre-irradiated pwr rod, 10 fresh fuel rods, and one instrument thimble containing a dummy steel rod. the boilaway of the coolant will permit heatup of the rods to the point of rapid cladding oxidation with concomitant cladding melting, partial fuel liquefaction, fuel oxidation, hydrogen generation, and fission product release. the hydrogen generation (from the oxidation reaction), the bundle temperatures, the liquid level, and the fission product release will be monitored during the test. the melt progression will be assessed using post test visual and metallographic examination results. experience from similar flht tests is combined with analysis results to show that: 1) high-temperature material will be contained within the shroud that surrounds the rod array, precluding damage to the nru loop pressure tube; 2) the released fission products and hydrogen will be contained and disposed of by the effluent control system in a manner that poses no unresolved safety hazard to operating personnel or to the public; and 3) the radiation exposure to operating personnel and to the public will remain below approved control limits.
Author: A. R. Causey
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Book Description
The possibility of accelerating creep at low temperature in annealed zircaloy at high fluences, similar to previously reported growth 'breakaway' behaviour at temperatures above 500 k, has been investigated at 340 k using stress relaxation and irradiation growth tests on annealed zircaloy-4 pre-irradiated at 580 k to 5 x 10sup(24) and 8 x 10sup(25) n.m-2 e1 mev. test results suggest that both creep and growth rates are higher for the specimens pre-irradiated to the higher fluence, however, the stress relaxation data are not conclusive. the presence of c component dislocations, revealed by transmission electron microscopy, only in the high fluence material has been related previously to the growth 'breakaway' at 580 k, and appears to result in higher growth and creep rates at 340 k.
Author: George P. Sabol
Publisher: ASTM International
ISBN: 0803124066
Category : Nuclear fuel claddings
Languages : en
Pages : 907
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Book Description
Author: Atomic Energy of Canada Limited
Publisher: Chalk River, Ont. : Chalk River Nuclear Laboratories
ISBN:
Category :
Languages : en
Pages : 21
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Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 930
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Author: R. A. Holt
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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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. A. Holt
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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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: R. W. L. Fong
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Book Description
The possibility of accelerating creep at low temperature in annealed zircaloy at high fluences, similar to previously reported growth 'breakaway' behaviour at temperatures above 500 k, has been investigated at 340 k using stress relaxation and irradiation growth tests on annealed zircaloy-4 pre-irradiated at 580 k to 5 x 10sup(24) and 8 x 10sup(25) n.m-2 e1 mev. test results suggest that both creep and growth rates are higher for the specimens pre-irradiated to the higher fluence, however, the stress relaxation data are not conclusive. the presence of c component dislocations, revealed by transmission electron microscopy, only in the high fluence material has been related previously to the growth 'breakaway' at 580 k, and appears to result in higher growth and creep rates at 340 k.
