Performance and inspection of zirconium alloy fuel bundle components in light water reactors (LWRs) - Materials' Ageing and Degradation in Light Water Reactors - page 200

Dry storage
criteria

USA Germany Hungary S. Korea

(CANDU only)

Spain (follows
USNRC)

Switzerland

Failed fuel
defi nition

NUREG-1536
Rev 1a (ISG1,
rev. 2)

Any assembly with
defected rods

Failed assembly
identifi ed by sipping

Clad penetration
that emits
fi ssion
products

NRC ISG1, rev. 1 None

Failed fuel
placement
in storage
cask

NUREG-1536
Rev 1a
(ISG1, rev.
2)

Yes in special
container
(ZIRAT11/IZNA6,
Sect. 11.3.2)

Not approved Not approved Yes, case by case

to meet safety
criteria

Not approved

Reactivity
requirement
(max, K eff )

0.95 0.95 normal 0.97

accidents

0.95 0.95 <1

K eff + Δ K eff 0.95

BU credit Yes, with

actinides
& fi ssion
products

Yes, with actinides
& fi ssion
products

No; storage is based
on enrichment of
fresh fuel

“ none ” Yes, with

actinides,
only for
transportation
license

Yes, acceptable
for
transportation
license

Analysing with
fl ooding

Ye s Ye s Ye s “ none ” Ye s Ye s

Moderator
exclusion
claim

No, likely No No “ none ” No No

Worst accident
assumed

9 m cask drop 9 m cask drop PSA approach for

max. radioactive
exposure

Coincident
failure of
“ cylinder ”
and 600
CANDU
assemblies

No criticality
in transport
accident with
fl ooding

Airplane crash +
kerosene fi re,
earthquake
for storage
+ 9m drop
etc. for
transport

( Continued )