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light water reactors

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Series: ASM Handbook
Volume: 13C
Publisher: ASM International
Published: 01 January 2006
DOI: 10.31399/asm.hb.v13c.a0004147
EISBN: 978-1-62708-184-9
... Abstract This article examines the understanding of persistent material changes produced in stainless alloys during light water reactor (LWR) irradiation based on the fundamentals of radiation damage and existing experimental measurements. It summarizes the overall trends and correlations...
Series: ASM Handbook
Volume: 13C
Publisher: ASM International
Published: 01 January 2006
DOI: 10.31399/asm.hb.v13c.a0004148
EISBN: 978-1-62708-184-9
... Abstract The components used in light water reactors (LWR) often remain in contact with the primary coolant, whose typical temperatures and pressures are highly aggressive, therefore, initiating corrosion in most of the alloys. This article describes the corrosion behavior of zirconium alloys...
Series: ASM Handbook
Volume: 13C
Publisher: ASM International
Published: 01 January 2006
DOI: 10.31399/asm.hb.v13c.a0004223
EISBN: 978-1-62708-184-9
... Abstract This article reviews a series of serious corrosion problems that have plagued the light water reactor (LWR) industry. It discusses the complex corrosion mechanisms involved, and the development of practical engineering solutions for their mitigation. The article contains tables...
Image
Published: 01 January 2006
Fig. 15 Dependence of radiation-induced segregation on homologous temperature and dose rate for austenitic stainless steels. LWR, light water reactor More
Series: ASM Handbook
Volume: 1
Publisher: ASM International
Published: 01 January 1990
DOI: 10.31399/asm.hb.v01.a0001036
EISBN: 978-1-62708-161-0
...-energy neutrons during operation. However, irradiation damage from neutrons is also a factor in commercial light-water reactors, even though neutrons in a light-water reactor are moderated to reduce their energy (most neutrons in the spectrum of these reactors are thermal neutrons with energies much...
Image
Published: 01 January 2006
Fig. 14 Summary of irradiation-assisted stress-corrosion cracking (IASCC) in light water reactors and associated metallurgical changes in austenitic stainless steels as a function of neutron irradiation in n/cm 2 ( E ≥1 MeV) or displacements per atom (dpa). EFPY, effective full power year More
Series: ASM Handbook
Volume: 20
Publisher: ASM International
Published: 01 January 1997
DOI: 10.31399/asm.hb.v20.a0002471
EISBN: 978-1-62708-194-8
... to improve corrosion awareness and prevent corrosion/degradation. It describes a life prediction method with an example of environmental degradation in light-water nuclear reactors. The article concludes with a discussion on the validation of life-prediction algorithms and their applications. aqueous...
Series: ASM Handbook
Volume: 13C
Publisher: ASM International
Published: 01 January 2006
DOI: 10.31399/asm.hb.v13c.a0004145
EISBN: 978-1-62708-184-9
... , 28 , 29 , 30 ) since this depletion, together with irradiation-induced metalloid segregation, can further reduce the IGSCC resistance over that associated solely with thermal sensitization. See the article “Effect of Irradiation on Corrosion and Stress-Corrosion Cracking in Light Water Reactors...
Series: ASM Handbook
Volume: 13C
Publisher: ASM International
Published: 01 January 2006
DOI: 10.31399/asm.hb.v13c.a0004146
EISBN: 978-1-62708-184-9
... reactors pitting pressurized water reactor high-strength stainless steels primary water circuits secondary water circuits steam generator denting external bolting corrosion primary circuit radiation fields A PRESSURIZED WATER REACTOR (PWR) is a type of nuclear reactor that uses ordinary light...
Series: ASM Handbook
Volume: 13C
Publisher: ASM International
Published: 01 January 2006
DOI: 10.31399/asm.hb.v13c.a0004144
EISBN: 978-1-62708-184-9
... bundles of 2 to 4% enriched uranium dioxide fuel pellets stacked in zirconium alloy cladding tubes. This Section deals with corrosion issues in light water reactors, research on the corrosion mechanisms, and the development and implementation of engineering solutions. The burial of spent fuel that has...
Series: ASM Handbook
Volume: 5B
Publisher: ASM International
Published: 30 September 2015
DOI: 10.31399/asm.hb.v05b.a0006035
EISBN: 978-1-62708-172-6
... of Nuclear Power Plants This article focuses on coatings used in the two basic types of Generation 3 nuclear reactor designs in the United States: the boiling water reactor (BWR) and the pressurized water reactor (PWR). Both are cooled by deionized water (light water or H 2 O) and use enriched uranium...
Series: ASM Handbook
Volume: 8
Publisher: ASM International
Published: 01 January 2000
DOI: 10.31399/asm.hb.v08.a0003328
EISBN: 978-1-62708-176-4
... ( Ref 1 ) contains some C and m values for different R -ratios of typical steels of light water reactors. Threshold stress-intensity values for selected materials Table 1 Threshold stress-intensity values for selected materials Material ASTM designation German designation Threshold...
Series: ASM Handbook
Volume: 4C
Publisher: ASM International
Published: 09 June 2014
DOI: 10.31399/asm.hb.v04c.a0005843
EISBN: 978-1-62708-167-2
..., reactors, and other magnetic products to the induction heating industry. These may operate from line frequency to approximately 800 kHz. Many of these products, because of the power and frequency range covered and the usual constraints of cost and physical size, are water cooled. The range of products...
Series: ASM Handbook
Volume: 13A
Publisher: ASM International
Published: 01 January 2003
DOI: 10.31399/asm.hb.v13a.a0003610
EISBN: 978-1-62708-182-5
... to lithium at 1000 °C (1830 °F) for 2 h. Light micrograph. Etched with 25% HF, 12.5 HNO 3 , 12.5% H 2 SO 4 in water. Source: Ref 8 Fig. 16 Iron crystals found in a plugged region of a failed pump channel of a lithium processing test loop. Multifaceted platelike crystals are ∼0.4 mm (0.015...
Series: ASM Handbook
Volume: 24A
Publisher: ASM International
Published: 30 June 2023
DOI: 10.31399/asm.hb.v24A.a0006964
EISBN: 978-1-62708-439-0
... K.L. , Gollapudi S. , Ramaswamy K. , Mathew M.D. , and Charit I. , Creep Deformation of Materials in Light Water Reactors (LWRs) , Materials Ageing and Degradation in Light Water Reactors: Mechanisms and Management , Woodhead Publishing Ltd. , 2013 , p 81 – 148 10.1533...
Series: ASM Handbook
Volume: 6
Publisher: ASM International
Published: 01 January 1993
DOI: 10.31399/asm.hb.v06.a0001441
EISBN: 978-1-62708-173-3
... in water, followed by a thorough clean-water rinse and air drying. A joint cleaned by degreasing can still be covered by a very light oil film that is approximately the equivalent thickness of the residue left by fingerprints. This can be effectively removed by abrasive or detergent cleaning, using...
Series: ASM Handbook
Volume: 2
Publisher: ASM International
Published: 01 January 1990
DOI: 10.31399/asm.hb.v02.a0001084
EISBN: 978-1-62708-162-7
... excellent resistance to many corrosive media, including superheated water, and it is transparent to thermal energy neutrons. These properties prompted the U.S. Navy to use zirconium in water-cooled nuclear reactors as cladding for uranium fuel. In 1958, zirconium became available for industrial use...
Series: ASM Handbook
Volume: 5A
Publisher: ASM International
Published: 01 August 2013
DOI: 10.31399/asm.hb.v05a.a0005711
EISBN: 978-1-62708-171-9
... Abstract Nuclear power plants benefit from thermal spray coatings for corrosion and erosion minimization and dimensional restoration of worn parts. This article provides a detailed discussion on the advantages of thermal spray coatings, fission reactor component coatings, and coatings...
Series: ASM Handbook
Volume: 9
Publisher: ASM International
Published: 01 December 2004
DOI: 10.31399/asm.hb.v09.a0003782
EISBN: 978-1-62708-177-1
..., with its high neutron cross section and corrosion resistance similar to zirconium in high-temperature water and steam environments, is used as nuclear reactor control rods and has been used for reprocessing of spent nuclear fuel. Zirconium also finds use in flashbulbs, incendiary devices, sputtering...
Series: ASM Handbook
Volume: 5B
Publisher: ASM International
Published: 30 September 2015
DOI: 10.31399/asm.hb.v05b.a0006026
EISBN: 978-1-62708-172-6
... in an operating boiling water reactor (BWR) or pressurized water reactor (PWR) nuclear plant is the design-basis accident that causes the reactor fuel to become partially or completely dewatered. When this condition occurs, the uncontrolled release of heat energy and radioactivity from the reactor core will soon...