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Nuclear power reactors

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Series: ASM Technical Books
Publisher: ASM International
Published: 01 January 2017
DOI: 10.31399/asm.tb.sccmpe2.t55090191
EISBN: 978-1-62708-266-2
.... , and Perks J.M. , State of Knowledge of Radiation Effects on Environmental Cracking in Light Water Reactor Core Materials , Proc. 4th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors , National Association of Corrosion Engineers , 1990 6.2...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 January 2017
DOI: 10.31399/asm.tb.sccmpe2.t55090359
EISBN: 978-1-62708-266-2
.... Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, 1984 16.4 “ Failures in 4-Inch Bypass Piping of Dresden 2 ,” NRC IE Bull. No. 74-10B, U.S. Nuclear Regulatory Commission, Office of Inspection and Enforcement, 1975 16.5 “ ASME Boiler and Pressure Vessel Code ,” Section XI...
Book Chapter

By Kenneth A. Walsh
Series: ASM Technical Books
Publisher: ASM International
Published: 01 July 2009
DOI: 10.31399/asm.tb.bcp.t52230001
EISBN: 978-1-62708-298-3
... was selected as a reflector or moderator in nuclear reactors. Quantities of beryllium used in reactors ranged from a few kilograms in systems for nuclear auxiliary power devices to 1600 kg in the Advanced Test Reactor at Idaho National Laboratory. Until the cessation of nuclear weapon construction, large...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 January 2017
DOI: 10.31399/asm.tb.sccmpe2.t55090349
EISBN: 978-1-62708-266-2
... 39 , 1977 , p 232 – 240 15.2 “ Investigation and Evaluation of Cracking in Austenitic Stainless Steel Piping of Boiling Water Reactor Plants ,” Tech. Report NUREG 75/067, U.S. Nuclear Regulatory Commission, Oct 1975 15.3 Klepfer H.H. et al. , Investigation of Causes...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 January 2017
DOI: 10.31399/asm.tb.sccmpe2.t55090135
EISBN: 978-1-62708-266-2
.... , and Van J.C. Duysen, Stress Corrosion Cracking Behavior of Nickel-Base Alloys With 19% Chromium in High Temperature Water , Proc. 3rd Int. Symp. Environmental Degradation of Materials In Nuclear Power Systems—Water Reactors , Theus G.J. and Weeks J.R. , Ed., The Metallurgical Society...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 December 2006
DOI: 10.31399/asm.tb.cw.t51820177
EISBN: 978-1-62708-339-3
...—Water Reactors (Lake Tahoe, NV) , Aug 5–9 , 2001 , Ford F.P. and Was G. , Ed., NACE International 31. Fukushima Daiichi Nuclear Power Station Unit 3 , “Primary Loop Recirculation System Work Report for Pipe Branches Replacement,” paper presented at BWR Operating Plant...
Book Chapter

Series: ASM Technical Books
Publisher: ASM International
Published: 01 November 2007
DOI: 10.31399/asm.tb.htcma.t52080409
EISBN: 978-1-62708-304-1
...General applications of molten salt technology in several industries Table 15.1 General applications of molten salt technology in several industries Industry Applications Power Solar/thermal: collection, storage, transfer Nuclear: homogeneous reactors, reprocessing...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 December 2015
DOI: 10.31399/asm.tb.cpi2.t55030074
EISBN: 978-1-62708-282-2
... D. , Rios R. , and Vaillant F. , Corrosion Deformation Interaction During Stress-Corrosion Cracking of Alloy 600 in Primary Water , Proceedings of Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , TMS , 1993 , p 669...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 January 2017
DOI: 10.31399/asm.tb.sccmpe2.t55090095
EISBN: 978-1-62708-266-2
...-temperature water SCC usually denotes SCC in simulated nuclear boiling water reactor (BWR) and nuclear pressurized water reactor (PWR) coolant environments. The term irradiation-assisted SCC refers to SCC in nuclear power station core components that are subjected to heavy doses of radiation within...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 November 2007
DOI: 10.31399/asm.tb.htcma.t52080423
EISBN: 978-1-62708-304-1
... been investigated for use as coolants in nuclear reactors. Sodium, for example, has been used as a coolant in fast breeder nuclear reactors. Most corrosion studies of molten metals have been carried out in conjunction with nuclear reactor applications ( Ref 1 – 4 ). Other applications of liquid metals...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 June 2008
DOI: 10.31399/asm.tb.emea.t52240597
EISBN: 978-1-62708-251-8
... superheated water, and is almost transparent to thermal energy neutrons. These properties, combined with its good mechanical properties, make zirconium very useful in nuclear power applications, especially as cladding for uranium fuel and for other reactor components. Zirconium and most of its alloys...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 November 2010
DOI: 10.31399/asm.tb.sap.t53000117
EISBN: 978-1-62708-313-3
... equipment, heating-element sheathing, nuclear steamgenerator tubing Good strength and excellent oxidation and carburization resistance Incoloy 800H Chemical and petrochemical processing, superheater and reheater tubing in power plants, industrial furnaces, heat treating equipment Based on IN-800...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 January 2017
DOI: 10.31399/asm.tb.sccmpe2.t55090303
EISBN: 978-1-62708-266-2
... corrosion resistance. For more than 60 years, zirconium and its alloys have been successfully used in a variety of applications, including fuel cladding and structural components in nuclear reactors, chemical equipment, getters, and alloying. Zirconium resists stress-corrosion cracking (SCC) in certain...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 December 1989
DOI: 10.31399/asm.tb.dmlahtc.t60490001
EISBN: 978-1-62708-340-9
... fossil fuels in a boiler or from the heat produced by atomic reactions inside a nuclear reactor. It is estimated that in the United States approximately 70% of the electricity is produced in fossil power plants, 15% in nuclear power plants, 12% in hydroelectric power plants, and the remainder from other...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 October 2011
DOI: 10.31399/asm.tb.mnm2.t53060315
EISBN: 978-1-62708-261-7
... is not as ductile or as easily worked, while the ductility of zirconium is similar to stainless steel and allows fabrication with common shop equipment. Zirconium and hafnium are used in water-cooled nuclear reactors, but they serve different functions. Zirconium allows passage of thermal neutrons, while...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 April 2013
DOI: 10.31399/asm.tb.imub.t53720233
EISBN: 978-1-62708-305-8
... portable Accelerator 10 3 –10 6 Medium Average On-off operation, medium cost, possibly transportable Subcritical assembly 10 4 –10 6 Good Average Stable operation, medium to high investment cost, movement difficult Nuclear reactor 10 5 –10 8 Excellent Short Medium to high investment...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 July 2009
DOI: 10.31399/asm.tb.bcp.t52230131
EISBN: 978-1-62708-298-3
.... , Paine R.M. , and Stonehouse A.J. , 1964 . Studies on the Vapor Pressure and Oxidation of Certain Beryllides , Compounds of Interest in Nuclear Reactor Technology , sponsored by The Metallurgical Society of AIME, at the University of Colorado , p 477 – 493 Brady M.P...
Book Chapter

Series: ASM Technical Books
Publisher: ASM International
Published: 01 October 2012
DOI: 10.31399/asm.tb.lmub.t53550193
EISBN: 978-1-62708-307-2
... it especially compatible with nuclear energy and fusion reactor applications. Low levels of iron and aluminum are present in commercial grades of beryllium ( Table 4.2 ). Although these elements cannot be eliminated economically, they can be balanced, and heat treatments can be applied to form discrete...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 August 2018
DOI: 10.31399/asm.tb.msisep.t59220475
EISBN: 978-1-62708-259-4
.... “ Alternative Welding Methods, XI Rules for Inservice Inspection of Nuclear Power Plant Components ,” IWA-4600, Boiler & Pressure Vessel Code 2015 edition, ASME , 2015 35. Ashby M.F. and Easterling K.E. , A First Report on Diagrams for Grain Growth in Welds , Acta Metall. , Vol 30...
Book Chapter

Series: ASM Technical Books
Publisher: ASM International
Published: 01 December 1989
DOI: 10.31399/asm.tb.dmlahtc.t60490021
EISBN: 978-1-62708-340-9
... Annealing and Surveillance of Reactor Pressure Vessels , Vienna, Austria , Feb 26 – 28 , 1979 (cited in Ref 48) 38. Server W.L. and Oldfield W. , “ Nuclear Pressure Vessel Steel Data Base, ” EPRI-933, Electric Power Research Institute , Palo Alto, CA , Dec 1978 10.2172/6471958...