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Book Void precipitate Association During Neutron Irradiation of Austenitic Stainless Steel

Download or read book Void precipitate Association During Neutron Irradiation of Austenitic Stainless Steel written by and published by . This book was released on 1986 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Microstructural data has recently become available on a single heat of 316 stainless steel irradiated in EBR-II and HFIR, over a wide range of irradiation temperature (55 to 750°C), dose (7 to 75 dpa), and helium generation rate (0.5 to 55 at. ppM He/dpa). Extensive information on precipitate compositions and characteristics are included. The data reveal several important relationships between the development of voids and precipitation. Precipitate associated voids dominate the swelling of (DO heat) 316 at 500 to 650 C from 8.4 to 36 dpa in EBR-II. Cold work (CW) or helium preinjection delay void formation in EBR-II. Higher helium generation in HFIR also delays void formation at 500 to 640°C in SA 316 and CW DO heat 316. The delay persists in CW 316 at least to 61 dpa in HFIR, but abundant matrix and precipitate-associated voids form in SA after 47 dpa. In another heat of CW 316 (N-lot) irradiated in HFIR matrix and precipitate voids form readily after 22 to 44 dpa at 500 to 600°C.

Book Dependence of Void Formation on Phase Stability in Neutron Irradiated Type 316 Stainless Steel

Download or read book Dependence of Void Formation on Phase Stability in Neutron Irradiated Type 316 Stainless Steel written by HR. Brager and published by . This book was released on 1979 with total page 26 pages. Available in PDF, EPUB and Kindle. Book excerpt: The void swelling rate in Type 316 steel is dominated by the instantaneous composition of the austenite matrix rather than by the concurrent nature of the dislocation and void microstructure alone. This is the conclusion derived from a series of neutron-irradiation experiments designed to determine which microstructural components account for the variability of void development observed in this alloy in response to changes in composition, preirradiation treatment, and irradiation history. The attainment of steady-state swelling is thought to be related to the development of a saturation microstructure of precipitates and dislocations. The existence of a saturation state for dislocation microstructure has been confirmed, but this condition is reached at fluences substantially below the onset of steady-state swelling. Relative to a solution-annealed treatment, 20 percent cold working accelerates the approach to saturation of the dislocation microstructure; thus the delay of swelling by cold work cannot be rationalized simply in terms of the time or fluence dependence of dislocation density.

Book Void Swelling and Microstructure of Austenitic Stainless Steels Irradiated in the BOR   60 Reactor

Download or read book Void Swelling and Microstructure of Austenitic Stainless Steels Irradiated in the BOR 60 Reactor written by and published by . This book was released on 2012 with total page 79 pages. Available in PDF, EPUB and Kindle. Book excerpt: As nuclear power plants age and neutron fluence increases, detrimental effects resulting from radiation damage have become an increasingly important issue for the operational safety and structural integrity of core internal components. In this study, irradiated specimens of reactor core internal components were characterized by transmission electron microscopy. The specimens had been irradiated to 5.5-45 dpa in the BOR-60 reactor at a dose rate close to 10-6 dpa/s and temperature of about 320°C. No voids were observed in the austenitic stainless steels and nickel alloys at all doses. Despite the possibility that fine voids below the TEM resolution limit may be present, it was clear that void swelling was insignificant in all examined alloys up to 45 dpa. Irradiated microstructures of the studied alloys were dominated by a high density of Frank loops. The mean size and density of the Frank loops varied from one material to another, but saturated with increasing dose above ~10 dpa. While no irradiation-induced precipitations were present below 24.5 dpa, fine precipitates were evident in several alloys at 45 dpa.

Book Radiation Processes in Crystal Solid Solutions

Download or read book Radiation Processes in Crystal Solid Solutions written by Gennadi Gladyshev and published by Bentham Science Publishers. This book was released on 2012-03-31 with total page 108 pages. Available in PDF, EPUB and Kindle. Book excerpt: Radiation Processes In Crystal Solid Solutions is a monograph explaining processes occurring in two classes of crystal solids (metal alloys and doped alkali halides) under irradiation by various types of radiation (alpha, beta, gamma, X-radiations, ions). While metal alloys may differ in high radiation stability, solid solutions based on alkali halides are very radiation-sensitive materials. Radiation defect production mechanisms, intrinsic and extrinsic radiation defects, a role of complexes an impurity-radiation defect which explain distinction in radiating stability of the specified classes of solid solutions are discussed in this e-book. To describe radiation induced phase transformations, two approaches are highlighted: kinetic and thermodynamic. This e-book also includes research on the effect of small radiation doses in a structurally solid phase state of a solution along with a semi-quantitative estimation of radiation effects with respect to temperature changes. This e-book should be a useful reference for advanced readers interested in the physics of radiation and solid state physics.

Book Dimensional Stability and Mechanical Behaviour of Irradiated Metals and Alloys

Download or read book Dimensional Stability and Mechanical Behaviour of Irradiated Metals and Alloys written by British Nuclear Energy Society and published by . This book was released on 1983 with total page 228 pages. Available in PDF, EPUB and Kindle. Book excerpt: Sessions at this conference were entitled: 'Micro-structural Development and Void Swelling', 'In-reactor Creep', 'High Temperature Mechanical Properties', 'Thermal Reactor Materials' and 'Design and Performance of Reactor Components and Structures'.

Book Irradiation induced Precipitation in a Niobium stabilised Stainless Steel

Download or read book Irradiation induced Precipitation in a Niobium stabilised Stainless Steel written by Shepherd J.P. and published by . This book was released on 1969 with total page 6 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Nuclear Science Abstracts

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975 with total page 1550 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Effects of Second Phase Particles on Irradiation Swelling of Austenitic Alloys

Download or read book Effects of Second Phase Particles on Irradiation Swelling of Austenitic Alloys written by WK. Appleby and published by . This book was released on 1973 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: Results are described from the investigation of swelling caused by fast-neutron-induced void formation in stainless steel fuel cladding and high-nickel alloys irradiated in fast flux (EBR-II) to fluences up to 7.3 x 1022 n/cm2, E > 0.1 MeV. Immersion density measurements of swelling gave results ranging from a volume increase of 10 percent in solution-annealed Type 347 stainless steel to a small densification in Inconel-625. Transmission electron microscopy investigations revealed that the extent of void formation in Types 316 and 347 stainless steels, Incoloy-800, and Hastelloy-X was related to the degree of intragranular precipitation (principally carbides), whereas the Ni3 Cb precipitation in Inconel-625 had apparently inhibited void formation altogether. It is concluded that precipitate particles can play a major role in determining the extent of void formation in austenitic alloys during neutron irradiation, and in the optimum morphology (a high concentration of closely spaced, small and possibly coherent particles) they offer promise of largely inhibiting void formation and swelling.

Book Void Swelling and Microstructural Change in Neutron Irradiated Type 316 Stainless Steel

Download or read book Void Swelling and Microstructural Change in Neutron Irradiated Type 316 Stainless Steel written by M. Itoh and published by . This book was released on 1987 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Microstructural observations were made on cold-worked Type 316 stainless steel following fast neutron irradiation to a peak neutron fluence of 1.3 x 1027 n/m2 (E > 0.1 MeV) at temperatures from 400 to 620°C. The results show that nickel depletion in the matrix after neutron irradiation is related to the formation of phosphides and void swelling. Phosphorus in solution retards not only the recovery of dislocations but also the development of nickel- and silicon-rich phases, and this results in suppressing nickel depletion in the matrix and an extension of the transient regime in void swelling. Phosphides are formed during the transient regime at temperatures from 490 to 570°C. After phosphides are formed, retardation effects on both dislocation recovery and the formation of nickel- and silicon-rich phases are lost, and this leads to the onset of void swelling.

Book Energy Research Abstracts

Download or read book Energy Research Abstracts written by and published by . This book was released on 1985 with total page 664 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book In reactor Precipitation and Ferritic Transformation in Neutron  irradiated Stainless Steels

Download or read book In reactor Precipitation and Ferritic Transformation in Neutron irradiated Stainless Steels written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Ferritic transformation (.gamma. .-->. .cap alpha.) was observed in Type 304L, 20% cold-worked AISI 316, and solution-annealed AISI 316 stainless steels subjected to fast neutron irradiation. Each material demonstrated an increasing propensity for transformation with increasing irradiation temperature between 400 and 550°C. Irradiation-induced segregation of Ni solute to precipitates was found not to influence the transformation kinetics in 304L. Similar composition data from 316 materials demonstrates a much greater temperature dependence of precipitation reactions in the process of matrix Ni depletion during neutron irradiation. The 316 data establishes a strong link between such depletion and the observed .gamma. .-->. .cap alpha. transformation. Moreover, the lack of correlation between precipitate-related Ni depletion and the .gamma. .-->. .cap alpha. transformation in 304L can be related to the fact that irradiation-induced voids nucleate very quickly in 304L steel during irradiation. These voids present preferential sites for Ni segregation through a defect trapping mechanism, and hence Ni segregates to voids rather than to precipitates, as evidenced by observed stable .gamma. shells around voids in areas of complete transformation.

Book Irradiation induced Precipitation in a Niobium stabilized Stainless Steel

Download or read book Irradiation induced Precipitation in a Niobium stabilized Stainless Steel written by J. P. SHEPHERD and published by . This book was released on 1969 with total page 6 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Irradiation Creep and Stress enhanced Swelling of Fe 16Cr 15Ni Nb Austenitic Stainless Steel in BN 350

Download or read book Irradiation Creep and Stress enhanced Swelling of Fe 16Cr 15Ni Nb Austenitic Stainless Steel in BN 350 written by and published by . This book was released on 1997 with total page 200 pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiation creep and void swelling will be important damage processes for stainless steels when subjected to fusion neutron irradiation at elevated temperatures. The absence of an irradiation device with fusion-relevant neutron spectra requires that data on these processes be collected in surrogate devices such as fast reactors. This paper presents the response of an annealed austenitic steel when exposed to 60 dpa at 480°C and to 20 dpa at 520°C. This material was irradiated as thin-walled argon-pressurized tubes in the BN-350 reactor located in Kazakhstan. These tubes were irradiated at hoop stresses ranging from 0 to 200 MPa. After irradiation both destructive and non-destructive examination was conducted.

Book ERDA Energy Research Abstracts

Download or read book ERDA Energy Research Abstracts written by and published by . This book was released on 1985 with total page 676 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book INIS Atomindex

Download or read book INIS Atomindex written by and published by . This book was released on 1987 with total page 866 pages. Available in PDF, EPUB and Kindle. Book excerpt: