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Breeder reactors

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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
... observations have indicated that thermal neutrons can also cause irradiation effects. Therefore, material damage from neutron irradiation is important not only in fast reactors, such as the experimental Fast Flux Test Facility (FFTF) in Hanford, Washington, and the Super Phenix fast-breeder electric power...
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
... on the sodium-cooled fast breeder reactor. This concept led to large-scale research and development programs that have continued through more than two decades. The result is a vast wealth of knowledge related to sodium corrosion behavior in all its varied aspects. The body of information greatly overshadows...
Series: ASM Handbook
Volume: 13A
Publisher: ASM International
Published: 01 January 2003
DOI: 10.31399/asm.hb.v13a.a0003594
EISBN: 978-1-62708-182-5
... of such applications include molten sodium for liquid metal fast breeder reactors and central receiver solar stations as well as liquid lithium for fusion and space nuclear reactors. In addition, tritium breeding in deuterium-tritium fusion reactors necessitates the exposure of lithium atoms to fusion neutrons...
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
... Ensembles Nucleaires (AFCEN) 10. French Design and Construction Rules for Mechanical Components of Fast Breeder Reactors (RCC-M), Association Francaise pour la Construction des Ensembles Nucleaires (AFCEN) 11. “Unfired Fusion Weld Pressure Vessels,” BS 5500, British Standard Institution 12...
Series: ASM Handbook
Volume: 13B
Publisher: ASM International
Published: 01 January 2005
DOI: 10.31399/asm.hb.v13b.a0003824
EISBN: 978-1-62708-183-2
... (UNS R04251 or R04261, reactor or commercial grade) is a corrosion-resistant niobium alloy with corrosion resistance similar to that of pure niobium, except with higher strength imparted by the addition of zirconium. In most applications where pure niobium is used, Nb-1Zr can be applied using higher...
Series: ASM Handbook
Volume: 19
Publisher: ASM International
Published: 01 January 1996
DOI: 10.31399/asm.hb.v19.a0002404
EISBN: 978-1-62708-193-1
Series: ASM Handbook Archive
Volume: 11
Publisher: ASM International
Published: 01 January 2002
DOI: 10.31399/asm.hb.v11.a0001818
EISBN: 978-1-62708-180-1
Series: ASM Handbook
Volume: 11A
Publisher: ASM International
Published: 30 August 2021
DOI: 10.31399/asm.hb.v11A.a0006812
EISBN: 978-1-62708-329-4
Series: ASM Handbook
Volume: 18
Publisher: ASM International
Published: 31 December 2017
DOI: 10.31399/asm.hb.v18.a0006410
EISBN: 978-1-62708-192-4
Book Chapter

Series: ASM Handbook Archive
Volume: 11
Publisher: ASM International
Published: 01 January 2002
DOI: 10.31399/asm.hb.v11.a0003562
EISBN: 978-1-62708-180-1
... Components,” this is a problem frequently encountered in heat exchangers, where pipes or fuel rod containers are restrained by supports or baffles but experience vibration as a result of fluid flow. Two types of wear can be distinguished in the practical case encountered in nuclear reactors. The first...
Series: ASM Handbook
Volume: 14B
Publisher: ASM International
Published: 01 January 2006
DOI: 10.31399/asm.hb.v14b.a0005127
EISBN: 978-1-62708-186-3
... reactor components. Contact forming is often used in these situations, because even the availability of an appropriate pool may be problematic. Concrete dies are often used to set the stage. Dimensional Tolerance Like any manufacturing process, the dimensional tolerance or reproducibility one can...
Series: ASM Handbook Archive
Volume: 11
Publisher: ASM International
Published: 01 January 2002
DOI: 10.31399/asm.hb.v11.a0003553
EISBN: 978-1-62708-180-1
... chloride environment at 95 °C (200 °F). Cracks are branching and transgranular. (b) Caustic SCC in the HAZ of a type 316L stainless steel NaOH reactor vessel. Cracks are branching and intergranular. There are exceptions to the general rule that stress-corrosion cracks are branched. For example, some...
Series: ASM Handbook
Volume: 4D
Publisher: ASM International
Published: 01 October 2014
DOI: 10.31399/asm.hb.v04d.a0005959
EISBN: 978-1-62708-168-9
... of the Kolsterizing treatment are not publicly known, it is most likely that Kolster found inspiration for this treatment in a corrosion mechanism observed in liquid-metal fast breeder reactors (LMFBR), where the interaction between AISI 316 and liquid sodium (as a coolant) resulted in unwanted carburizing...
Series: ASM Handbook
Volume: 1
Publisher: ASM International
Published: 01 January 1990
DOI: 10.31399/asm.hb.v01.a0001035
EISBN: 978-1-62708-161-0
... for elevated-temperature service are manganese-molybdenum-nickel ferritic steels (ASTM A 302 and A 533), which are commonly used for pressure vessels in light-water reactors. High-alloy steels, stainless steels, hot-work tool steels, and the iron-base superalloys are discussed in the Section “Specialty Steels...
Series: ASM Handbook
Volume: 20
Publisher: ASM International
Published: 01 January 1997
DOI: 10.31399/asm.hb.v20.a0002467
EISBN: 978-1-62708-194-8
..., University of Tokyo. 2-11-16 Yayoi, Bunkyo-ku, Tokyo 113, Japan. Tel: 81-3-3812-2111. Generic data on all engineering materials, nuclear fuel data, fusion reactor materials data, industrial standards for metals and alloys, high-temperature superconducting materials (P) C. Robb, Metals Databook...
Series: ASM Handbook
Volume: 17
Publisher: ASM International
Published: 01 August 2018
DOI: 10.31399/asm.hb.v17.a0006450
EISBN: 978-1-62708-190-0
Series: ASM Handbook
Volume: 1
Publisher: ASM International
Published: 01 January 1990
DOI: 10.31399/asm.hb.v01.a0001009
EISBN: 978-1-62708-161-0