Austenitic Stainless Steel as a Fuel Element Cladding PDF Download
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Author: Alton Schmitt
Publisher:
ISBN:
Category :
Languages : en
Pages : 150
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Author: Alton Schmitt
Publisher:
ISBN:
Category :
Languages : en
Pages : 150
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Author: T. J. Pashos
Publisher:
ISBN:
Category : Metal cladding
Languages : en
Pages : 120
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Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
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The combination of metallic fuel and stainless steel cladding in a fuel element forms a complex multicomponent diffusion couple at elevated temperatures. Interdiffusion of fuel and cladding components can in principle lead to several phenomena that could affect the reliable performance of a fuel element. These phenomena include the formation of strength reducing diffusion zones in the cladding, intergranular penetration of fuel components into the cladding, and the formation of compositional zones with melting points below the anticipated operating temperatures. A series of ex-reactor tests were performed to assess and study this potential problem in fuel elements consisting of U-Zr, U-Pu-Zr fuel clad in Ti stabilized austenitic stainless steel (D9) and ferritic stainless steel (HT-9). Diffusion couples of various combinations of fuel and the different steels were annealed at temperatures ranging from 650°C to 800°C for up to 3000 h in an argon atmosphere. The post-test analysis of the diffusion couples included: metallographic examinations, scanning electron microscopy, and scanning Auger microscopy.
Author: E. L. Long (Jr.)
Publisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 38
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Author: W. K. Barney
Publisher:
ISBN:
Category : Ferritic steel
Languages : en
Pages : 28
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Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 17
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Interdiffusion experiments have been conducted to investigate the compatibility of various austenitic stainless steels with U-Pu-Zr alloys, which are alloys to be employed as fuel for the Integral Fast Reactor being developed by Argonne National Laboratory. These tests have also studied the compatibility of austenitic stainless steels with fission products, like the minor actinides (Np and Am) and lanthanides (Ce and Nd), that are generated during the fission process in an IFR. This paper compares the results of these investigations in the context of fuel-cladding compatibility in IFR fuel elements, specifically focusing on the relative Interdiffusion behavior of the components and the types of phases that develop based on binary phase diagrams. Results of Interdiffusion tests are assessed in the light of observations derived from post-test examinations of actual irradiated fuel elements.
Author:
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Category :
Languages : en
Pages :
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This invention describes a composition for an austenitic stainless steel which has been found to exhibit improved high temperature stress rupture properties. The composition of this alloy is about (in wt. %): 12.5 to 14.5 Cr; 14.5 to 16.5 Ni; 1.5 to 2.5 Mo; 1.5 to 2.5 Mn; 0.1 to 0.4 Ti; 0.02 to 0.08 C; 0.5 to 1.0 Si; 0.01 maximum, N; 0.02 to 0.08 P; 0.002 to 0.008 B; 0.004-0.010 S; 0.02-0.05 Nb; 0.01-0.05 V; 0.005-0.02 Ta; 0.02-0.05 Al; 0.01-0.04 Cu; 0.02-0.05 Co; 0.03 maximum, As; 0.01 maximum, O; 0.01 maximum, Zr; and with the balance of the alloy being essentially iron. The carbon content of the alloy is adjusted such that wt. % Ti/(wt. % C+wt. % N) is between 4 and 6, and most preferably about 5. In addition the sum of the wt. % P+wt. % B+wt. % S is at least 0.03 wt. %. This alloy is believed to be particularly well suited for use as fast breeder reactor fuel element cladding.
Author: W. K. Winegardner
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 48
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This report was prepared in response to a Fast Flux Test Facility (FFTF) Division request for information and recommendations concerning the decay storage of irradiated fuel elements. The report first summarizes information concerning irradiated fuel element storage techniques. This summary is followed by a discussion of information related to fuel cladding corrosion problems that conceivably could result from decay storage after in-core exposure. Finally, all of the information, obtained primarily by literature review, is used as the basis for recommendations concerning storage media. The work was prompted by concern over possible loss of fuel element cladding integrity during decay storage in air or water. The concern ranges from effects that could hinder fuel examination to those that could result in local regions of cladding penetration or even failure while handling fuel. This report is primarily related tot he latter type of effect, since the facility is viewed simply as a cell or basin where fuel elements can safely be stored prior to chemical processing.
Author: United States. Congress Senate
Publisher:
ISBN:
Category :
Languages : en
Pages : 1456
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Author: United States. Congress. Senate. Committee on Appropriations
Publisher:
ISBN:
Category : Finance, Public
Languages : en
Pages : 1464
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