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boiling water reactor

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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 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...
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 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...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 December 2006
DOI: 10.31399/asm.tb.cw.t51820177
EISBN: 978-1-62708-339-3
... 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, types of weld corrosion issues, and prevention or mitigation strategies...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 December 2006
DOI: 10.31399/asm.tb.cw.t51820203
EISBN: 978-1-62708-339-3
...) Electrochemical Impedance Spectroscopy (EIS) Electrochemical Noise (EN) Corrosion Potential Ultrasonic Thickness Measurements Ultrasonic Testing of Welds in the ByPass Lines of a Boiling Water Reactor Other NDT Techniques Tests for Stainless Steels and Nickel-Base Alloys ASTM G 48 ASTM G...
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
...-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 January 2017
DOI: 10.31399/asm.tb.sccmpe2.t55090135
EISBN: 978-1-62708-266-2
... for Pressurized Water Reactor Steam Generator Tubing , Nucl. Technol. , Vol 55 , 1981 , p 88 – 104 10.13182/NT81-A32833 5.79 Jones R.L. , Long R.L. , and Olszewski J.S. , “ The Origin of the Extensive Cracking of the Steam Generator Tubing at TMI Unit 1 ,” Paper 141, presented...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 December 2015
DOI: 10.31399/asm.tb.cpi2.t55030074
EISBN: 978-1-62708-282-2
.... , Boursier J.-M. , Noel 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...
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
... Boiling 0.003 0.12 Chloroform 100 Boiling 0.000 0.000 Chloroform + water 50 Boiling 0.12 4.8 Cyclohexane + traces of formic acid … 150 302 0.0003 0.12 Ethyl alcohol 95 Boiling 0.013 0.52 Ethylene dichloride 100 Boiling <0.13 <5.2 Formaldehyde 37 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
... … • … … … … … … … Ammonia, aqueous … … • … … … … … … Bromine … … … … … … … … • Carbonates, aqueous … • … … … … … … … Carbon monoxide, carbon dioxide, water mixture … • … … … … … … … Chlorides, aqueous • … … • • • … … • Chlorides, concentrated, boiling...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 January 2017
DOI: 10.31399/asm.tb.sccmpe2.t55090303
EISBN: 978-1-62708-266-2
.... A condition of “dry-out” is a possible occurrence in nuclear reactors. Dissolved salts in water could precipitate out under this condition. Certain SCC tests have been performed on zirconium alloys in possibly aggressive salts ( Ref 11.12 , 11.13 ). Results indicated that split-ring specimens of Zircaloys...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 December 2015
DOI: 10.31399/asm.tb.cpi2.t55030292
EISBN: 978-1-62708-282-2
... in Petrochemical Reactor Vessel Steels (July 1981) API 950 Survey of Construction Materials and Corrosion in Sour Water Strippers (1978) API 956 Hydrogen Assisted Crack Growth in 2.25Cr-1Mo Steel (March 1978) API 959 Characterization Study of Temper Embrittlement of Chromium-Molybdenum Steels (1982...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 August 2018
DOI: 10.31399/asm.tb.msisep.t59220475
EISBN: 978-1-62708-259-4
.... Furthermore, special applications require medium or low alloyed steels similar to engineering steels. This is the case for such as steels for nuclear reactor pressure vessels, high-pressure vessels, submarine hulls, and so on. A large part of the world’s use of steel encompasses structural steels...
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.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 December 1989
DOI: 10.31399/asm.tb.dmlahtc.t60490001
EISBN: 978-1-62708-340-9
... field containing conducting wires (stator), as shown schematically in Fig. 1.1 ( Ref 3 ). Rotation of the shaft is achieved by coupling it to a turbine in which the kinetic energy of a moving fluid is converted into mechanical energy of rotation. The working fluid can be wind, water, steam...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 July 2009
DOI: 10.31399/asm.tb.bcp.t52230459
EISBN: 978-1-62708-298-3
.... , and Gibson P. , 1963 . “ The Corrosion of Beryllium and Some Beryllium Alloys by High-Temperature Steam ,” Report AERE-R-4422, U.K. Atomic Authority • English J.L. , 1949 . “ Interim Report on the Corrosion of Beryllium in Simulated Cooling Water for the Proposed Development Reactor...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 December 2015
DOI: 10.31399/asm.tb.cpi2.t55030126
EISBN: 978-1-62708-282-2
.../0010-9312-28.9.321 35. Jones R.H. , Some Radiation Damage-Stress Corrosion Synergisms in Austenitic Stainless Steels , Proceedings of the Second International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , American Nuclear Society, Sept...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 December 2015
DOI: 10.31399/asm.tb.cpi2.t55030062
EISBN: 978-1-62708-282-2
... 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 crack very rapidly in the polythionic...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 July 2009
DOI: 10.31399/asm.tb.bcp.t52230093
EISBN: 978-1-62708-298-3
... are most often the critical contaminants. This pitting has been correlated to the alloy impurity distribution occurring at sites with high concentrations of iron, aluminum, or silicon [ Wright and Silver 1963 ]. Beryllium reacts readily with H 2 SO 4 and HCl. Boiling water and alkalis react...