Performance and inspection of zirconium alloy fuel bundle components in light water reactors (LWRs) - Materials' Ageing and Degradation in Light Water Reactors - page 201

Table 5.1 (continued)

Dry storage
criteria

USA Germany Hungary S. Korea

(CANDU only)

Spain (follows
USNRC)

Switzerland

Fuel failure
allowed in
worst case
accident

Yes Yes Yes No failure during

cooling
blockage

Yes, within off-site
dose limits

Ye s

Acceptable
failure
conditions

10CFR72 &
source
term limit

10% failed rods
1% fuel release

Retrievability
Criticality
Coolability

- % fuel failures

1% - normal
10% - off
normal 100%
- accident +
maintain max
cask internal
pressure

Retrievability

Modelling
codes

ABACUS
LS DYNA
FALCON

MCNP MCP4, SCALE 5.1,

MONK 6B, RISK
SPECTRUM,
TRANSURANUS,
ENIGMA + others

- MCNP, SCALE,

ANSYS,
FLUENT
ABACUS, LS
DYNA 3D

CSAS (AREVA)
for normal
conditions

ANT International, 2011

* Differences in the allowable cladding stress among fuel vendors and plants was identifi ed through private communication subsequent to
the survey (Hellwig, 2011).