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Nuclear reactor components, corrosion

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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
... BWR Component IGSCC Behavior on Coolant Chemistry , Proc. 4th Int. Conf. Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors , National Association of Corrosion Engineers , 1990 , p 14-46 to 14-62 6.7 Brown K.S. and Gordon G.M. , Effects of BWR...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 January 2017
DOI: 10.31399/asm.tb.sccmpe2.t55090359
EISBN: 978-1-62708-266-2
... for Inservice Inspection of Boiling Water Reactor (BWR) Piping Welds with Intergranular Stress Corrosion Cracking (IGSCC) , Proc. 8th Int. Conf. NDE in the Nuclear Industry , ASM International , 1987 In 1982, intergranular SCC was found in large-diameter stainless steel piping, which prompted...
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 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 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...
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 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 January 2017
DOI: 10.31399/asm.tb.sccmpe2.t55090135
EISBN: 978-1-62708-266-2
... and Corrosion Cracking of Materials for Water Cooled Reactors ,” EPRI Progress Reports FCC7805 ( Jan–June 1980 ), Electric Power Research Institute 5.141 Berge P. , “ Modeling Corrosion for Life Prediction of Nuclear Reactor Components ,” Paper 1, presented at Int. Symp. Life Prediction...
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 November 2010
DOI: 10.31399/asm.tb.sap.t53000117
EISBN: 978-1-62708-313-3
... corrosive environments and is especially resistant to pitting and crevice corrosion Inconel 690 … Resists nitric and hydrofluoric acids Inconel 718 GTE components, rocket motors, spacecraft, nuclear reactor pumps, and tooling Most widely used of all wrought superalloys. Creep rupture strength up...
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...
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
... h at 690 to 730 °C (1280 to 1350 °F) ( Ref 27 ). Corrosion of alloys in molten fluoride salts has been extensively studied for nuclear reactor applications. The molten salt nuclear reactor uses a LiF-BeF 2 base salt as a fuel salt, containing various amounts of UF 4 , ThF 4 , and ZrF 4 ( Ref...
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 October 2011
DOI: 10.31399/asm.tb.mnm2.t53060315
EISBN: 978-1-62708-261-7
.... Niobium and tantalum have high melting points and are also classified as refractory metals. Hafnium and zirconium are similar in terms of chemical properties, such as resistance to corrosion in nuclear environments and high strength. Nonetheless, there are two significant differences: Hafnium...
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 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 2015
DOI: 10.31399/asm.tb.cpi2.t55030235
EISBN: 978-1-62708-282-2
... production (urea) reactors 450–500 840–930 Nitriding Other processes Titanium production reactor vessels 900 1650 Oxidation, chlorination Nitric acid—catalyst grid 930 1705 Oxidation, nitriding, sulfidation Nuclear reprocessing reactors 750–800 1380–1470 Oxidation (steam...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 December 2006
DOI: 10.31399/asm.tb.cw.t51820143
EISBN: 978-1-62708-339-3
... Nuclear and nonnuclear grades of zirconium alloys Table 6 Nuclear and nonnuclear grades of zirconium alloys Alloy design Composition, wt% UNS No. Zr+Hf (a) Hf (b) Sn Nb Fe Cr Ni Fe+Cr Fe+Cr+Ni O (b) Nuclear grades Zircaloy-2 R60802 ... 0.01 1.20–1.70 ... 0.07–0.2...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 July 2009
DOI: 10.31399/asm.tb.bcp.t52230131
EISBN: 978-1-62708-298-3
... at Intermediate Temperatures—Anomalous Behavior and a Solution , Symposium on Components of Interest in Nuclear Reactor Technology , AIME-TMS , Warrensdale, PA , p 495 – 509 , 1964 Perkins F.C. , 1963 . “ Intermediate Temperature Oxidation of Beryllides, Final Report ,” University of Denver...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 April 2013
DOI: 10.31399/asm.tb.imub.t53720233
EISBN: 978-1-62708-305-8
... STP 586 emphasize the value of neutron radiography for inspection of ordnance, explosive, aerospace, and nuclear components. The presence, absence, or correct placement of explosives, adhesives, O-rings, plastic components, and similar materials can be verified. The presence of fluids or corrosion can...