The latest in this popular series provides 44 peer-reviewed papers on the latest international research covering all aspects of zirconium alloy properties and performance relevant to the nuclear industry.
Topics address:
All aspects of the fuel cycle
Basic metallurgy
Spent fuel
Corrosion
Mechanical properties
Deformations mechanisms
Failure mechanisms
LOCA and Transients.
These papers provide examples of studies where experimental techniques are combined with analytical tools and calculations; reflect a stronger trend towards efforts that enable fundamental in-reactor measurements, which are essential for further development of experimental techniques as well as for the possibility to enhance the development of improved alloys; and examine an increasing number of alternative alloys being developed and verified.
STP1505-C01
STP1505-C02
STP1505-C03
STP1505-C04
STP1505-C05
STP1505-C06
STP1505-C07
STP1505-F01
STP1505-F02
STP1505-R01
STP1505-R02
STP1505-R03
STP1505-SN
STP 1505
STP1505
STP1505
STP1505
STP 1505