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Book A Study of Neutron Irradiation in Alpha Iron and A 1Cr 0 5Mo Pressure Vessel Steel

Download or read book A Study of Neutron Irradiation in Alpha Iron and A 1Cr 0 5Mo Pressure Vessel Steel written by B. L. Eyre and published by . This book was released on 1963 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: A considerable amount of work has been carried out to determine the influence of neutron irradiation on the mechanical properties of iron and steels; the principal effects--namely, increases in yield stress and decreases in ductility in tension tests and increases in transition temperature in notched-bar tests-- have now been established (1). The effects of the irradiation (integrated neutron dosage, temperature of irradiation, neutron dosage rate, and flux spectrum) and metallurgical (type of steel, grain size, and so on) variables have now been appreciated (2,3), but little progress has been made in identifying the nature of the damage responsible for the property changes.

Book The Journal of the Iron and Steel Institute

Download or read book The Journal of the Iron and Steel Institute written by Iron and Steel Institute and published by . This book was released on 1964 with total page 606 pages. Available in PDF, EPUB and Kindle. Book excerpt: Includes the institute's Proceedings.

Book Analysis of the Behaviour of Advanced Reactor Pressure Vessel Steels Under Neutron Irradiation

Download or read book Analysis of the Behaviour of Advanced Reactor Pressure Vessel Steels Under Neutron Irradiation written by International Atomic Energy Agency and published by . This book was released on 1986 with total page 144 pages. Available in PDF, EPUB and Kindle. Book excerpt: The final report of an IAEA co-ordinated research programme involving nine organizations in eight Member States during the period 1977-1983. The irradiation response of seven steels typical of modern practice, in the form of plants, forgings and submerged arc welds supplied by worldwide suppliers, was determined under light water reactor pressure vessel irradiation conditions.

Book Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels

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:

Book Analysis of the Behaviour of Advanced Reactor Pressure Vessel Steels Under Neutron Irradiation

Download or read book Analysis of the Behaviour of Advanced Reactor Pressure Vessel Steels Under Neutron Irradiation written by International Atomic Energy Agency and published by . This book was released on 1986 with total page 119 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Transactions

    Book Details:
  • Author : Iron and Steel Institute
  • Publisher :
  • Release : 1964
  • ISBN :
  • Pages : 926 pages

Download or read book Transactions written by Iron and Steel Institute and published by . This book was released on 1964 with total page 926 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Investigation of Neutron Irradiated Reactor Pressure Vessel Steel by Positron Annihilation and Electron Microscopy

Download or read book Investigation of Neutron Irradiated Reactor Pressure Vessel Steel by Positron Annihilation and Electron Microscopy written by RV. Nandedkar and published by . This book was released on 1987 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: Positron lifetime, annihilation line shape, and electron microscopic measurements have been carried out on neutron irradiated pressure vessel steel (HSST Plate 03) meeting ASTM A533-B (Unified Numbering System [UNS] K12539). The positron annihilation parameters for specimens irradiated at 423 K to a dose of 1.5 x 1018 n/cm2 are found to decrease sharply during the post-irradiation annealing interval, 473 to 623 K. This correlates well with the stage seen in the recovery of Vickers hardness. On the basis of known evidence for carbon migration in ?-iron and the interpretation of present results, enhancement and recovery of radiation hardening have been qualitatively understood in terms of formation and dissolution of carbon decorated vacancy complexes.

Book Irradiation of Some Pressure Vessel Steels

Download or read book Irradiation of Some Pressure Vessel Steels written by Atomic Energy of Canada Limited and published by . This book was released on 1959 with total page 35 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book A SURVEY OF THE EFFECTS OF NEUTRON IRRADIATION ON THE IMPACT AND OTHER MECHANICAL PROPERTIES OF PRESSURE VESSEL STEELS FOR THE SM 2 REACTOR

Download or read book A SURVEY OF THE EFFECTS OF NEUTRON IRRADIATION ON THE IMPACT AND OTHER MECHANICAL PROPERTIES OF PRESSURE VESSEL STEELS FOR THE SM 2 REACTOR written by and published by . This book was released on 1960 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A literature survey on the effects of neutron irradiation on impact and other mechanical properties of both ferritic steels and austenitic stainless steels is presented. The materials studied included carbon and low alloy steels such as: ASTM A-212B, ASTM A-201, ASTM A-301B (CR-Mo), ASTM A-106 (coarse and fine grained), ASTM A-285, ASTM A-302B (Mn-Mo), ASTM A-353, ASTM A-203, Grade D, E-7016 carbon steel weld metal, USS Carilloy T-1, HY-65, and HY-80. Types 304 and 347 stainless steels were investigated as representative austenitic materials which might be used in pressure vessel construction. An evaluation was made of the irradiation induced changes in the mechancal properties of the above materials. The ferritic steels were evaluated primarily on the basis of increases in transition temperature due to irradiation and decreases in the amount of maximum energy absorbed prior to ductile failure. Factors such as industrial experience, changes in other mechanical properties, and the susceptibility of these materials to temper embrittlement were considered. Austenitic stainless steels were evaluated on the basis of post-irradiation and low temperature impact strength and on irradiation induced changes in other mechanical properties. It is concluded that austenitic stainless steels are capable of resisting harmful property damage at integrated neutron fluxes> 1 Mev of at least 1 to 2 x 10/sup 21/ nvt. Most carbon or low alloy steels with the exception of ASTM A-212B, were subject to severe property damage at exposures in excess of 1 x 10/sup 19/ nvt. With the application of special reactor operating procedures, it was determined that ASTM A-212B will be satisfactory at integrated neutron fluxes up to 5 x 10/sup 19/ nvt. (auth).