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welded boiling water reactor

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Published: 01 January 2017
Fig. 16.1 Cross section of a boiling water reactor (BWR) piping weld removed from service More
Series: ASM Technical Books
Publisher: ASM International
Published: 01 January 2017
DOI: 10.31399/asm.tb.sccmpe2.t55090349
EISBN: 978-1-62708-266-2
... Abstract This chapter examines the stress-corrosion cracking (SCC) failure of stainless steel pipe welds in boiling water reactor (BWR) service. It explains where most of the failures have occurred and provides relevant details about the materials of construction, fabrication techniques...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 January 2017
DOI: 10.31399/asm.tb.sccmpe2.t55090359
EISBN: 978-1-62708-266-2
... Abstract This chapter describes how ultrasonic testing came to be a viable method for evaluating intergranular stress-corrosion cracking (SCC) in large-diameter stainless steel pipe welds in boiling water reactor service. Intergranular SCC can be difficult to detect using nondestructive...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 December 2006
DOI: 10.31399/asm.tb.cw.t51820177
EISBN: 978-1-62708-339-3
... Abstract This chapter reviews weld corrosion in three key application areas: petroleum refining and petrochemical operations, boiling water reactor piping systems, and components used in pulp and paper plants. The discussion of each area addresses general design and service characteristics...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 December 2015
DOI: 10.31399/asm.tb.cpi2.t55030074
EISBN: 978-1-62708-282-2
... was the same as the corrosion rate of an unaged alloy when tested in boiling 10% NaOH (caustic solution) ( Ref 21 ). Changes in the Corrosion Rate of Alloy N06022 as a Consequence of Second-Phase Precipitation Figures 2(a) and (b) show the corrosion rate of wrought and gas tungsten arc welded (GTAW...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 December 2006
DOI: 10.31399/asm.tb.cw.t51820203
EISBN: 978-1-62708-339-3
... of Welds in the ByPass Lines of a Boiling Water Reactor One of the typical applications of ultrasonic testing is the in-service inspection of the coolant circuit pipes and the by-pass lines in a boiling water reactor. These pipes, which are fabricated from type 316 stainless steel, are intended...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 January 2017
DOI: 10.31399/asm.tb.sccmpe2.t55090191
EISBN: 978-1-62708-266-2
... exposure, which alters many material properties and produces radiolysis of water. Classic examples of the neutronfluence dependence of IASCC of austenitic stainless steel are shown in Fig. 6.2(a) ( Ref 6.6 , 6.7 ) for control-blade sheath cracking in high-conductivity boiling water reactors (BWRs...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 January 2017
DOI: 10.31399/asm.tb.sccmpe2.t55090095
EISBN: 978-1-62708-266-2
... 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 the core as well...
Book Chapter

Series: ASM Technical Books
Publisher: ASM International
Published: 01 January 2015
DOI: 10.31399/asm.tb.tpmpa.t54480331
EISBN: 978-1-62708-318-8
... 390 0.000 0.000 Aniline hydrochloride 5–20 35/100 95/212 <0.001 <0.04 Benzene + HCl + NaCl Vapor + liquid 80 176 0.005 0.2 Carbon tetrachloride 99 Boiling 0.003 0.12 100 Boiling 0.003 0.12 Chloroform 100 Boiling 0.000 0.000 Chloroform + water 50 Boiling...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 December 2015
DOI: 10.31399/asm.tb.cpi2.t55030215
EISBN: 978-1-62708-282-2
... themselves. Many bolted agitator assemblies in reactors, as well as riveted wheels in centrifugal compressors, have failed catastrophically because the bolts or rivets did not have adequate strength or corrosion resistance. When welding is the joining method, the materials engineer is challenged...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 December 2015
DOI: 10.31399/asm.tb.cpi2.t55030292
EISBN: 978-1-62708-282-2
... to be the associated reduction in residual tensile stresses in the area of the weldment, and the reduction in hardness and changes in the carbide morphology of weld heat-affected zones (HAZ). For refinery reactor vessels, which operate at high temperatures and pressures, 2.25Cr-1Mo steel is widely used. For improved...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 December 2006
DOI: 10.31399/asm.tb.cw.t51820125
EISBN: 978-1-62708-339-3
... during high-purity water exposure in nuclear reactor steam generator primary side environments ( Ref 20 ). Microsegregation in the Fusion Zone of Autogenous Welds When a weld solidifies, an inhomogeneous dendritic structure forms. Solidification begins with the highest-melting-point liquid...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 December 1989
DOI: 10.31399/asm.tb.dmlahtc.t60490329
EISBN: 978-1-62708-340-9
... 4. Erwin W.E. and Kerr J.G. , “ The Use of Quenched and Tempered 2¼Cr-1Mo Steel For Thick Wall Reactor Vessels in Petroleum Refinery Processes: An Interpretive Review of 25 Years of Research and Application, ” Bulletin 275, ISSN 0043-2326, Welding Research Council, New York , Feb...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 January 2017
DOI: 10.31399/asm.tb.sccmpe2.t55090135
EISBN: 978-1-62708-266-2
..., bromides, iodides, and fluorides), sulfur-bearing compounds (such as H2S and sulfur-oxyanions), high-temperature and supercritical water, and caustics (such as NaOH), while accounting for temperature, composition, microstructure, properties, environmental contaminants, and other factors. The chapter also...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 December 2015
DOI: 10.31399/asm.tb.cpi2.t55030062
EISBN: 978-1-62708-282-2
... of sensitized austenitic stainless steels in boiling high-purity water containing oxygen has received a great deal of study. This seemingly benign environment has led to cracking of sensitized stainless steels in many boiling water nuclear reactors ( Ref 13 – 15 ). Sensitized stainless alloys of all types...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 December 2006
DOI: 10.31399/asm.tb.cw.t51820043
EISBN: 978-1-62708-339-3
... boiling water nuclear reactors. This subject is addressed in Chapter 10, “Weld Corrosion in Specific Industries and Environments.” Sensitized stainless alloys of all types crack very rapidly in the polythionic acid that forms during the shutdown of desulfurization units in petroleum refineries ( Ref...
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 2000
DOI: 10.31399/asm.tb.cub.t66910331
EISBN: 978-1-62708-250-1
... performance of a given material are listed in Table 2 . Checklist for materials selection Table 1 Checklist for materials selection Requirements to be met Properties (corrosion, mechanical, physical, appearance) Fabrication (ability to be formed, welded, machined, etc.) Compatibility...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 January 2017
DOI: 10.31399/asm.tb.sccmpe2.t55090419
EISBN: 978-1-62708-266-2
... of water and therefore for the concentration of caustic soda (NaOH) ( Ref 18.26 ). The advances in chemical inhibitors, thermomechanical processing, and the use of welded structures have contributed to eliminate most occurrences; nevertheless, caustic embrittlement remains a major concern in the paper...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 January 2017
DOI: 10.31399/asm.tb.sccmpe2.t55090043
EISBN: 978-1-62708-266-2
... steel pipelines. 2.3.10 Other Environments Stress-corrosion cracking has been a problem in low-alloy steels used in nuclear power water reactors ( Ref 2.136 – 2.138 ). The environment of interest in this case is high-purity water with a very low oxygen content. Although susceptibility appears...