Download or read book An Analysis of Radiation Effects in Model A533B Pressure Vessel Steels Containing Copper Phosphorus and Nickel Additions written by JT. Buswell and published by . This book was released on 1999 with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt: An existing database of small angle neutron scattering (SANS) spectra on a series of model A533B alloys containing various copper, phosphorus or nickel additions, before and after 290°C neutron irradiation to 3.1x1023 n.m-2 (E>1 MeV), is re-analysed using a Maximum Entropy computing procedure. Volume fraction -- particle size and number density data are produced for each alloy to characterize the irradiation-induced microstructural changes in terms of microvoids and/or precipitates of different sizes. The calculations are further refined by introducing a compositional dependence to the irradiation-induced precipitates, assumed to be of the type CuNiMn. The derived particle size distributions are characterized by narrow sharp peaks at ~2 nm diameter and broader peaks in the range 10-40 nm diameter. The analysis suggests that under irradiation the total volume fraction of precipitates increases with phosphorus content, and that there is an increase in volume fraction with increase in both copper and nickel content at constant phosphorus level. Most of the volume fraction increase in low-P steels arises from 1-4 nm diameter precipitates, whilst for high-P steels there is evidence of a significant increase in 4-50 nm diameter precipitates. Estimates of radiation hardening based on input of the SANS data into hardening models are in accord with measured values.

Download or read book Effects of Radiation on Materials written by R. K. Nanstad and published by ASTM International. This book was released on 1999 with total page 1135 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effects of Radiation on Materials written by Todd R. Allen and published by ASTM International. This book was released on 2006 with total page 411 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effects of Radiation on Materials written by Martin L. Grossbeck and published by ASTM International. This book was released on 2004 with total page 767 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effects of Radiation on Materials written by Stan T. Rosinski and published by ASTM International. This book was released on 2001 with total page 879 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effects of Radiation on Materials written by Arvind S. Kumar and published by ASTM International. This book was released on 1994 with total page 1319 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Significance of Nickel and Copper Content to Radiation Sensitivity and Postirradiation Heat Treatment Recovery of Reactor Vessel Steels written by J. R. Hawthorne and published by . This book was released on 1982 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effects of Nickel on Irradiation Embrittlement of Light Water Reactor Pressure Vessel Steels written by International Atomic Energy Agency and published by IAEA. This book was released on 2005 with total page 70 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication sets out the findings of a co-ordinated research project to determine the influence of the mechanism of the deterioration effect in radiation embrittlement of reactor pressure vessel steels with a high nickel content in nuclear power plants, including procurement of materials, determination of mechanical properties, irradiation and testing of specimens, and microstructural characterisation.

Download or read book Radiation Embrittlement of a PWR Vessel Steel written by C. Flavier and published by . This book was released on 1981 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nickel-manganese-molybdenum low-alloy steels are employed today for the beltline regions of French pressurized water reactor vessels subject to radiation embrittlement. Brittle ductile transition temperature shifts observed in Charpy V-notch tests were used to evaluate the effects of some elements on embrittlement. The role of residuals such as phosphorus, copper, and tin was carefully studied with special laboratory heats. The detrimental effects of phosphorus and copper were quantitatively determined, particularly for low copper content heats. Tin also appears to be undesirable. Silicon and nickel contents may be modified in the future. Their effects were examined. It was not possible to establish the role played by silicon. The detrimental effects of nickel additions were, however, clearly demonstrated. The effects of certain other oligoelements were also studied.

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1969 with total page 1106 pages. Available in PDF, EPUB and Kindle. Book excerpt: NSA is a comprehensive collection of international nuclear science and technology literature for the period 1948 through 1976, pre-dating the prestigious INIS database, which began in 1970. NSA existed as a printed product (Volumes 1-33) initially, created by DOE's predecessor, the U.S. Atomic Energy Commission (AEC). NSA includes citations to scientific and technical reports from the AEC, the U.S. Energy Research and Development Administration and its contractors, plus other agencies and international organizations, universities, and industrial and research organizations. References to books, conference proceedings, papers, patents, dissertations, engineering drawings, and journal articles from worldwide sources are also included. Abstracts and full text are provided if available.

Download or read book Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels written by Lendell E. Steele and published by ASTM International. This book was released on 1989 with total page 276 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book The Role of Some Alloying Elements on Radiation Hardening in Pressure Vessel Steels written by N. Igata and published by . This book was released on 1973 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: Recent trends in nuclear-pressure-vessel steels for light-water reactors have been toward Ni-Cr-Mo steels. The effect of minor elements--for example, copper and phosphorus--also has been investigated. In this study, the role of nickel, chromium, molybdenum, and copper was investigated to understand the irradiation behavior of pressure vessel steel, using internal friction measurement, transmission electron microscopy (TEM), and mechanical testing. The materials used were Fe-1Ni, Fe-0.25Cr, Fe-0.5Mo, and Fe-0.2Cu. They were annealed or quenched and irradiated 1 ~ 3 x 1019 nvt(>1MeV) at 60 C (140 F), and postirradiation annealing was performed in the range 150~450 C (302~842 F).

Download or read book Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels written by Lendell E. Steele and published by ASTM International. This book was released on 1986 with total page 303 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Survey of postirradiation heat treatment as a means to mitigate radiation embrittlement of reactor vessel steels written by J. R. Hawthorne and published by . This book was released on 1979 with total page 40 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Radiation Embrittlement and Annealing Recovery of CrNiMoV Pressure Vessel Steels with Different Copper and Phosphorus Content written by R. Havel and published by . This book was released on 1993 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: The influence of copper and phosphorus content on Charpy-V-notch impact energy, on dynamic fracture toughness, and on radiation hardening recovery of tensile and hardness properties by postirradiation annealing at different temperatures was explored for one commercial heat and six laboratory melts of CrNiMoV pressure vessel steels irradiated to 0.9 to 1.3 x 1023 n/m2 (E > 1 MeV) at 280°C.

Download or read book Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels written by Lendell E. Steele and published by ASTM International. This book was released on 1993 with total page 405 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effects of Neutron Irradiation on Precipitation in Reactor Pressure Vessel Steels written by RG. Faulkner and published by . This book was released on 2005 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: Several MnMoNi pressure vessel steels with varying Ni, Cu, and Mo contents have been investigated in the irradiated and unirradiated condition. Examination using analytical transmission electron microscopy was performed in order to understand more fully the nature of both the inter- and intra-granular precipitation in these alloys. In particular, attention has been paid to the carbide population, which exists in the material in addition to the copper precipitates, which have received detailed study elsewhere. The most dramatic revelations concern the discovery that fine, intra-granular (10 nm diameter) Fe3C particles are present in these steels, in addition to the normally expected copper-rich precipitates of a similar size. Neutron irradiation increases the volume fractions of inter- and intra-granular precipitation of all phases (Fe3C, Cu-rich, and Mo2C). Neutron irradiation has the least effect in increasing volume fraction in high Ni; high Cu alloys (WV). The effects of neutron irradiation on precipitation rates are greatest in low Ni; high Cu alloys (SG (SH)). Inter-granular precipitation is most prevalent in the high Ni; low Cu material (WF). It is significant that this material contains the least intra-granular fine-scale precipitation. This is probably because the Cu precipitation is minimal. Mo and C have an important influence on the amount of Mo2C phase formed, with large amounts being observed in high Mo-C, irradiated material (SH) (0.48 % Mo). These results are discussed in terms of various models for inter-and intra-granular precipitate nucleation and growth.