Environmental Engineering Reference
In-Depth Information
5
Performance and inspection of zirconium
alloy fuel bundle components in light
water reactors (LWRs)
P. RUDLING , ANT International, Sweden
and R. B. ADAMSON , Zircology Plus, USA
DOI
: 10.1533/9780857097453.2.246
Abstract
: This chapter highlights integral performance of zirconium
alloy fuel bundle components used in nuclear power light water reactors
(LWRs). In particular we focus on those behaviours which result in
performance issues, and in experimental techniques which are used to
quantify the performance. Details in this chapter complement those in the
previous chapter on the properties of in-reactor zirconium alloy materials.
Key words
: zirconium alloys, nuclear reactors, accidents, dimensional
stability, irradiation, mechanical properties, corrosion, inspection, high
burnup.
5.1
Introduction
The previous chapter described material properties of zirconium alloys in
light water reactors (LWRs). The performance of fuel bundle components is
often driven by a combination of singular material properties; for example,
mechanical strength and irradiation creep. This chapter extends material
behaviour to include integral performance of fuel bundle components such
as fuel rods, channels and guide tube assemblies under both normal opera-
tional and accident conditions. In all cases, component inspection is needed
to verify expected or explore abnormal performance. A thorough under-
standing of both material and component behaviour is needed to assure
safe and effi cient reactor operation.
5.2
Materials performance during normal
operational conditions
We proceed with sections covering ways in which materials perform during
normal operating conditions in the main reactor types.
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