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Boiling water reactors

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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 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...
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Published: 01 January 2017
Fig. 15.1 Schematic of boiling water reactor (BWR) recirculation piping system More
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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
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Published: 01 January 2017
Fig. 5.24 Effect of chromium content on SCC CGR in boiling water reactor (BWR) environment at 288 °C (550 °F) with 2 ppm O 2 and 30 ppb sulfate. Source: Ref 5.102 More
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...
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Published: 01 January 2017
Fig. 6.3 Irradiation-assisted stress-corrosion cracking of various alloys exposed to (a) boiling water reactor (BWR) and (b) pressurized water reactor (PWR) core environments as a function of total strain in an in situ continuous-swelling tube test. Source: Ref 6.22 , 6.23 , 6.59 More
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Published: 01 December 2015
Fig. 17 Variation in the average crack propagation rate in sensitized type 304 stainless steel in water at 288 °C (550 °F) with oxygen content. Data are from both constant extension rate (CERT) tests, constant load, and field observations on boiling water reactor piping. IGSCC, intergranular More
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Published: 01 January 2017
Fig. 1.19 Variation in the average crack propagation rate in sensitized type 304 stainless steel in water at 288 °C (550 °F) with oxygen content. Data are from constant-extension-rate testing, constant-load testing, and field observations on boiling water reactor piping. IGSCC, intergranular More
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Published: 01 January 2017
Fig. 6.2 Dependence of IASCC on fast neutron fluence for (a) creviced control-blade sheath in high-conductivity boiling water reactors (BWRs) ( Ref 6.6 ) and (b) as measured in slow-strain-rate tests at 3.7 × 10 −7 /s on preirradiated type 304 stainless steel in 288 °C (550 ° F) water ( Ref More
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 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.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...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 December 2015
DOI: 10.31399/asm.tb.cpi2.t55030074
EISBN: 978-1-62708-282-2
.... This was corroborated through potentiodynamic anodic polarization ( Ref 23 ) and through corrosion immersion tests in boiling HCl solutions contaminated with different levels of ferric ions ( Ref 21 ). Secondary Carbide Effect in the Resistance of UNS N06600 to SCC in High-Temperature Water Inconel 600 (UNS...
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...
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...
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 December 2015
DOI: 10.31399/asm.tb.cpi2.t55030215
EISBN: 978-1-62708-282-2
... localized pitting corrosion even before the anticipated service ( Fig. 1 ). The damage occurred during storage, because the new (replacement) stainless steel pipe sections were in direct contact with mists of brackish water that arose in an unsheltered location immediately adjacent to a marine estuary...
Series: ASM Technical Books
Publisher: ASM International
Published: 01 December 2015
DOI: 10.31399/asm.tb.cpi2.t55030292
EISBN: 978-1-62708-282-2
..., metal surfaces covered with (oftentimes, sulfur-containing) corrosion products will be exposed to air and moisture. This can lead to pitting and other forms of localized corrosion and stress-corrosion cracking unless preventive measures are implemented. When equipment is washed with water during...
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...