Download or read book High Temperature Neutron Irradiation Damage in Molybdenum and TZM written by and published by . This book was released on 1974 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Neutron Irradiation Damage in Molybdenum written by D.M. Maher and published by . This book was released on 1970 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Radiation Damage and Thermal Annealing of Defects in Molybdenum and Tungsten written by A. N. Ivanov and published by . This book was released on 1971 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt: Radiation damage to high temperature metal homologues of molybdenum and tungsten as a function of dose and the reactor irradiation temperature is investigated. The studies were conducted with polycrystalline specimens 99.9 percent pure in the case of molybdenum and 99.85 percent in the case of tungsten. Variation if the specific electric resistance was used as a measure of the radiation damage. The saturation effect of the radiation damage and the differences observed between the behavior of molybdenum and tungsten are discussed from the standpoint of the thermal stability of the radiation defects formed in them. The part played by radiation alloying when tungsten is irradiated with large thermal neutron doses is also discussed. A study is made of the thermal annealing of radiation defects in molybdenum and tungsten subjected to various irradiation doses at temperatures above room temperature. The similarity between the three recovery stages in the increase in specific electric resistance, observed during annealing in these metals, and the nature of the defects responsible for the recovery stages are discussed. The variation in fine crystal structure for molybdenum and tungsten during reactor irradiation and subsequent annealing is investigated. (Author).

Download or read book Neutron Irradiation Damage in Molybdenum written by M.E. Downey and published by . This book was released on 1964 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Low Dose Neutron Irradiation Damage in Molybdenum written by and published by . This book was released on 1983 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Saturation of Swelling in Neutron Irradiated Molybdenum and Its Dependence on Irradiation Temperature and Starting Microstructural State written by and published by . This book was released on 1993 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: Molybdenum and its alloys are of interest for potential fusion application due to their high melting point and relatively good thermal conductivities. The development of void superlattices during neutron irradiation appears to limit void swelling in pure molybdenum to values below 4% over a wide range of irradiation temperatures. The saturation value of swelling and the void superlattice parameter each appear to be somewhat dependent on temperature, but independent of the thermomechanical starting state. Formation of technetium and ruthenium by transmutation may also play some minor role in the microstructural evolution, but do not appear to be involved in the limitation of swelling.

Download or read book Dimensional Stability of Neutron Irradiated Molybdenum written by HI. Jang and published by . This book was released on 1975 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: Polycrystalline molybdenum specimens were irradiated to fast neutron fluences between 1.1 x 1019 neutrons (n)/cm2 and 1.0 x 1022 n/cm2 at a temperature range of 70 to 480°C. The irradiation-induced length changes and subsequent changes during postirradiation annealing were measured using a high vacuum dilatometer. The effects of neutron fluences, at reactor ambient temperature of ~70°C, were to increase the length changes up to the neutron fluence of ~1020 n/cm2 and then level off at the higher fluences. The length change data were compared with the resistivity data and the ratio of resistivity to length changes was calculated as 2.7 x 10-3 ?-cm.

Download or read book The Nature and Thermal Stability of Defects in Neutron Irradiated Mo and Mo 0 5 Ti written by Vinod K. Sikka and published by . This book was released on 1973 with total page 850 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1974 with total page 730 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Void Formation During High Temperature Post Irradiation Annealing of Molybdenum Neutron Irradiated at 60 C written by J.H. Evans and published by . This book was released on 1972 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book ERDA Energy Research Abstracts written by United States. Energy Research and Development Administration and published by . This book was released on 1977 with total page 900 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book A Comparison of the High Temperature Damage Structures in Accelerator and Reactor Irradiated Molybdenum written by JH. Evans and published by . This book was released on 1973 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: The damage structures produced in high-purity molybdenum by neutrons in a fast reactor and by 2-MeV nitrogen ions in an accelerator have been compared using transmission electron microscopy (TEM). The irradiations have been carried out in the temperature range 450 to 900 C (842 to 1652 F) and doses in the range 10 displacements per atom (dpa) to 200 dpa. Over these ranges the damage structures can be defined in terms of a dislocation component and a void component. Several features of the void structures are found to be independent of the method of damage production, although the dose rate differences affect the temperature range and lower threshold dose for the formation of visible voids. With regard to the dislocation component of the structures, there is a qualitative similarity in distribution of loops and network dislocations between the reactor- and accelerator-irradiated specimens. However, a detailed analysis of the nature of the loops reveals important differences. The loops in reactor-irradiated specimens are predominantly interstitial in nature whereas the loops in accelerator-irradiated specimens containing voids are predominantly vacancy in nature. This result is discussed in detail together with other aspects of the comparative study.

Download or read book DAMAGE IN MOLYBDENUM ASSOCIATED WITH NEUTRON IRRADIATION AND SUBSEQUENT POST IRRADIATION ANNEALING written by and published by . This book was released on 1963 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Molybdemum containing carbon was studied in an attempt to establish the combined effect of impurity content and neutron irradiation on the properties and structure of specific metals. Molybdenum foils were punched into discs and heat treated in vacuum. They were then slow-cooled and irradiated. After irradiation and subsequent decay of radioactivity to a low level the foils were subjected to x-ray diffraction measurements. Cold-worked foils with less than 10 ppm carbon showed no change in microstructure due to irradiation. Molybdenum foils that were annealed prior to irradiation showed spot defects. In foils containing up to 500 ppm carbon, it was concluded that the small loops present after irradiation are due to the clustering of point defects at interstitial carbon atoms, followed by collapse to form a dislocation loop. The amount of lattice expansion after irradiation was strongly dependent on impurity content. Neutron irradiation was found to reduce the number of active slip systems. (M.C.G.).

Download or read book Recovery of Lattice Expansion of Irradiated Molybdenum written by D. L. Gray and published by . This book was released on 1958 with total page 36 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Radiation Effects in Molybdenum and Molybdenum zirconium Alloy written by Kang-Yih Liou and published by . This book was released on 1979 with total page 422 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1972 with total page 628 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Structural Alloys for Nuclear Energy Applications written by Robert Odette and published by Newnes. This book was released on 2019-08-15 with total page 676 pages. Available in PDF, EPUB and Kindle. Book excerpt: High-performance alloys that can withstand operation in hazardous nuclear environments are critical to presentday in-service reactor support and maintenance and are foundational for reactor concepts of the future. With commercial nuclear energy vendors and operators facing the retirement of staff during the coming decades, much of the scholarly knowledge of nuclear materials pursuant to appropriate, impactful, and safe usage is at risk. Led by the multi-award winning editorial team of G. Robert Odette (UCSB) and Steven J. Zinkle (UTK/ORNL) and with contributions from leaders of each alloy discipline, Structural Alloys for Nuclear Energy Applications aids the next generation of researchers and industry staff developing and maintaining steels, nickel-base alloys, zirconium alloys, and other structural alloys in nuclear energy applications. This authoritative reference is a critical acquisition for institutions and individuals seeking state-of-the-art knowledge aided by the editors' unique personal insight from decades of frontline research, engineering and management. - Focuses on in-service irradiation, thermal, mechanical, and chemical performance capabilities. - Covers the use of steels and other structural alloys in current fission technology, leading edge Generation-IV fission reactors, and future fusion power reactors. - Provides a critical and comprehensive review of the state-of-the-art experimental knowledge base of reactor materials, for applications ranging from engineering safety and lifetime assessments to supporting the development of advanced computational models.