84
Fatigue
of the material
and influence
In the present content
work
on stage
room
II
FCGR
temeprature
the fatigue
the effect
crack
of temper
of a martensitic
using
compact
growth
behaviour
embrittlement stainless
tension
of the steels.
and residual steel
specimens.
hydrogen
has been
Graphs.
studied
numerical
at
data,
Asbstracts inside
surface
analysis 500 to
MWe
3%
The
Fast
Breeder
mechanisms quick
Test
(CRDM)
shut down
barriers
for
gripper
control
expected
when
for
tested
to confirm
during
its operational
fuel
Intent
a
of
period
ten
the creep-fatigue the detailed
testing
test set up for bellows Graphs,
generated for
ambient
at multiple
single
(for
relation, values
reasonably
is
and is aimed determined
I Al
proposed.
R-dependencies
successful
and 2219-T85
stage fatigue
for
least
growth
to be
in
numerical
which
the
815 K Model’
indicates
The advantage
(FCC)
of an FCC
data
relation involves
parameters
in the adjustable
proposed
equation
material,
are
3 I6
high
strength,
standing
light
weight,
exhibit
superalloys.
environment.
great
potential
In this study,
processed,
near-infinity
understand
the
interactions.
fatigue
the
high
to differentiate
dependent
crack
behaviour
in
the
form
>
1.0 Hz
of
superimposed 0.01~2Cil
upon
SS
In order low have
been
hold 7x
effects
and increased effects
with
a retardation
creep
under
indicated
loading
resulting
maximum
growth
closure
effect
by
crack
load,
whereas rates.
Graphs,
at
to
blunting that
minimum
due
photomicrographs,
at
the environmental of
closure
model
to fatigue,
ha\ creep
22 ref.
influence
(FCC)
of
microstructures, received II
microstructure
rate in Zr-2.5
was
namely
pressure found
to
FCG
a-grains
behaviour
tube material
were
be insensitive
to
of the existing
have
room
better
models.
selected
Graph\,
sensitive.
for
studied numerical
01 +
crack
On
FCG
FCG.
a\
rate in stage
the other
has been rationalized data,
and
hand,
Microstructure
near threshold
growth
Four different
P-annealed
for the study.
microstructures.
resistance
fatigue
was investigated.
S-annealed,
microstructure
of microstructures
temperature
tube material
P-quenched,
rate in stage I was strongly ahgned
on
Nb pressure
FCG
containing The
observed
with
the help
photomicrographs,
9 ref.
Fatigue crack growth studies on primary heat transport piping. Chattopodhyny, J., Duttci, B. K. and Kushwho. H.S. Trmsnctions of the Indian Institute cf M&r/s ( 1996) 49, 5277532 The
leak-before-break
primary levels
heat transport of
performs
LBB
analysis.
fatigue
crack
(LBB)
concept
(PHT)
piping
The growth
present study
is now
universally
of nuclear paper
power
deals
of a postulated
used
plants.
with
the
to design
There level
part-through
the
are three two
flaw
total
imposing
the
(n PFBR analysis’
outlet
wrth
‘Reduced
becauw
elastx
perof
Chnboch I\
. X25 K.
of performing
analysi\,
SS 3lhLN.
rules
hy
tempemturc
of this component
simple
in
inelastic
demonstrated
temperature,
Material:
axral
rewlts
Graph\,
\ignifcant
at
in an
numerical
at low
the
strain
pre-exposed under
mode
ranges
of
IO
and
I and
duratrons
tested
in wdium
condition\.
fatigue
in sodium
prior
range.
Graphs,
LCF
lives
rn hoth
using
a
conduc-
peak
tensile
found
to
for te\ts
the environments to he beneficial
Thi\
data.
were rate 01
and
Mere
proved
studied.
numerical
strain
at
and
tc\t\
of . 4. However.
to te\ting
ranges
tu 3000 h)
tests were
30 min
on
studic\
cycling
1.59,
interaction
in air up to by a factor
strain
(up
continuou\ The
time
steel.
at a constant
0.6,
of specunens
three
and hold
stainless
rn air cnvn-onment\.
of
live\
time
all
sodium
Creep-fatigue
holds
Exposure
life
and
form.
than those tested
fatigue
and
pre-agmg
316L(N)
conducted
strain
wave
hold
sodium. type
strain-controlled
total
fatigue
under
of liqurd
tests were
temion
comparable.
effect
vvds more
22 rel
Influence of prior thermal aging on creep and low cycle fatigue behaviour of forged thick section 9Cr-1Mo ferritic sheet at 793 K. Choud%ory. R.K.. Vr~vrnnmi. A., Smkrrm Rae. K.B.. Momm. Xl. mrrl Km/v JU/J, B. P. Trmcrrc~tionv of t/w Irrdim Iu\titrrtr of Mrtol\ CI YY6) 49. I7Y-48X Detailed prior
mvestigations
thermal
aging
9CrrI
thermally
LCF
793 K.
signiticant
granular LCF to
matertal
softening
particle
r&stance in atre\s
which on the
aged
intensity
tip
of
mode
under
m
mode\
obeying
aged material
has been ascrrhed mam
compared progressive
remained
cracking.
exten-
improved
mainly
crack
power-lau transgrunulnr
exhibited
The
LCF
to the reduction
caused
Photomicropraphs.
trans-
test condnrom
exhibited
thermally
cracks.
at
observed
rcmumed
all
behaciour
and
continw
\pccimens
to he higher
secondary
propagating
and xxondary
wa\
found
stress-strain
aged material
and TA
materials
and propagation higher
in quenched
controlled
failure
01
of thick
(SPWHT)
propertre\
wa\ TA
~nlluence
conducted
on SPWHT The
and
the
behaviour
treatment
coalewxrce
However, and
at the
decohesion
(ICF)
heat
rupture
material
cyclic
conditions.
decohesion
void
SPWHT
initiation
of thermally
particlc
performed
by
and similar
in both material sive
tests were
weld
investigated.
Both
The crack
Creep
m creep
conditions
of thermally
to understand
fatigue
post
variation
maternal.
out
cycle
at 793 K. Total-axral-strain
characterized
resistance
cyclic
simulated
tests have been
ductile
SPWHT
carried
and low
condrtiom
ous cycling the three
been
steel forging.
(Q + T),
aged (TA) No
have
on creep
MO ferritic
tempered
data.
Effect of microstructure on fatigue crack growth in Zr-2SNb alloy. Guncu!\‘, S., Dubey, J.S., Hay, A., Chnkrmortty, J.K.. Biswm. A.R. rrrrd Banerjre, S. Trnnstrctions of the Indian lnstitutr of Mernls(1996) 49, 5X-540 The
of
of modified
in sodium
triangular
relationship.
loads,
crack
superposition
interactions
trme
produced
be attributed
to enhance
A linear
the complex
hold
01.
crack
as a consequence
hold
appear
the
It is believed
of
blunting for
loads
range
of
under
be higher
section
crack-tip
in this material.
due to crack-tip
degradation.
might
in an interaction
growth
for
whrch
analy&
outlet
on aweceived The
conditions
In general.
and
frequency
degradation,
of
contidcnce
detailed
‘elastic
it i\
that reactor
temperature
1%.
the inHuence bchav,iour
IO 1s ‘/ employing
was used
a wide of
model
instead -
Whde
of. _ 770 K,
a viscoplatic
of
component
rules of RCCMR.
performed.
ORNL
analysis
conducted
time
technique
minimum
dependence
Superposition
and micro-cracking
to account
over
loading
and time-
testing
and
I .O Hz cyclic
rate,
level
results
applied
in lower
and ewironmental
strong
frequency.
of
intermetallics
performed a
range
A novel
maximum
environmental
load
crack-branching
employed
at
p-
analyzed
the cycle-dependent
aluminide
Experiments
asperity-induced
loads
times
in crack
at maximum
been
hold
of enhanced
time
extensive
titanium
and
nickel-base
has been
a wide
two
with-
alloys
cree~fatigueeenvironment
of this material.
loads over a baseline
variation
the combined
between
with
Further
at X23 K.
symmetrical
to
of an advanced
at 866 K
been
temperature
efficiency
fatigue
specimens
were
of safety
traditional
is found
perwd
the lwel
the most critical
that the permissible
to a\\ess
cycle
conducted
demand
titanium
behaviour
IO0
temperature
for
Hz
cyclic
and minimum
an insignificant
a hold
frequency.
from
rate
maximum
by the author
baseline
frequencies growth
growth
for
investigation,
was employed
employed
growth Ti-I
experimental
frequency earlier
capable
\atisfie\
life
I I ref.
conducted is
crack
applications
cotwentional
as replacement
alloy,
of
and other
materials
Some
crack
titanium
influence
During
nuclear
damage-tolerant
high temperature
intermetallica
to
and safety-critical
in thus caw
cntrre
Effect of flowing sodium and prior exposure to sodium on LCF and creep fatigue interaction behaviour of type 316 L(N) stainless steel. Mishrcr, M.P., Bor,qsredt. H. U., V~d~cm,M.. Mnnnnn. S.L. rrnd Rodri,yur;. P. 7‘nrrrsrrr~tion.rof r/w Irrdinrr ltrstitute of Mefal.> ( 1996) 49. 497-503
ted
Influence of creep-fatigue environment interactions on fatigue growth behaviour of Ti-1100 at elevated temperature. Porida, B. K. Tmnscrctions of‘ t/w /r,dinn brstifute of Metal.\ ( 1996) 49, S3 I~550 aerospace
the
two
to the
3 ref.
strain.
Advanced
Thi\
damage
of 55 K in the reactor
in plant
data.
plug.
have
the
is acceptable.
viscoplastic
with
cracA growth
during
level
5 ref..
fatigue
analysis
increase
I.1ref.
data,
inelastic
detaded
of the adjustable The
formmg
interaction
simplification
ht.
the control
the creep
programme
data.
the confidence
square
test cases
Graphs,
The
of some
at improving
by
two
alloy.
crack
(R) levels, a simplification
literature)
stipulated
in the FCC parameter
three
load ratio
R-level
incorporating
condition
with
for
Empirical correlation for three stage fatigue crack growth at multiple load ratio (R) levels in ambient conditions. Puckinraj, C.C., Ray, S.K. crnd Mmnm. S.L. Trcrruuctions of the hIdim Imtiturr qf Mernl.\ ( 1996) 49, 55 I -55Y For correlating
to qualrfy
analyses
together
numerical
In order
accordance
bc satisfied
The
data.
of the
by applying
Creep fatigue damage assessment of PFBR control plug. Chellnpondi, P.. Romrsh. R.. Chetrd, XC. end Bhojr. S.B. 7’rcmo~~tiorrt of the h&m Irruitutr of Mcml.~( 1996) 49. SOS-S I2
viwoplnatrc
of the reactor.
methodology demonstrated
fatigue
thickness of load.
numerical
can
with
wall
all combinations
Graphs,
complete
subsequently
Maximum
and
are
The
and
pipe
The
and
have
the
tight
years
manufacturers
satisfying
testing.
safe and leak
813 K
of
shut down
different
and the detailed
of creep-fatigue
rod drive
in the CRDM.
temperature
handling
of
control
and achieve
movements
over
from
level
are used as primary
stage. This paper describes
basis,
findings
service
CRDM
the design
and its theoretical the initial
spare
bellows
at maximum
every
uses \ix
power
and gripper
operate
during
procured
Metal
continuous
cycling
at IGCAR
the reactor
translatory
bellows
undergo
temperature
(FBTR)
desired.
facilitating
to
bellows
Reactor to control
pipings. here
PHWR.
of
under
of LBB.
Creep-fatigue testing of metal bellows in sodium. Bnlachnnder. K., Rujnn, K.K., Rnmnlingnm, P., Vijo,wshrre, M.. Guptcr. SK., Chellnpnndi, P., Chrml, SC. rmd Kolr, R.D. Trmscrctionr of thr Indian Insriture of Mrtnls ( 1996) 49, 595600
PHT
Indian
be i
reactor
6 ref.
of
is described
hy enhanced
graphs.
numerrcal
37 ref.
On the bilinearity in fatigue power-law relationships in aluminium-lithium alloys. Prosnd. N.E.. M&~kondcrroh. G. curd Kutmhnrrro. 1’.1’ I’rcmnctrons of the lrrdirrrr Imtituw of’Metals ( 1996). 49, 46.5364 The of
present Al-Li
law
with
alloys.
paper
alloy\. one
\et
Various
power-law
deal\ Such
with
bilmearity
a deviation
of constant\ metallurgical
relationships
III
in the fatigue
from
an (deal
become\ factors
Al-Li
important that
alloys
lead
power-law
behaviour in life to
the
are compiled
of
rclation\hip\ wgle
poww
predictions bdinearity
of there m
and discussed.
fatigue Graph\,
26 ref.
High temperature low cycle fatigue behaviour of titanium based alloys. Mnlnkondainh. G. und Nicholm, 7 Tron.wction.s of the Indim Imtirut~~ of Mrtul.! ( lY9h) 49. 36 1464 High
temperature
alloy
in
2Nb2Cr been
alloy
studied,
2Nb2Cr
alloy
iour.
the
On
low
cycle
basket-weave
fatigue
in fully~lamellar with
and
in FL basis
behaviour
microstructural
of
without
condition\ hysteretic
01. a Ti,Al-bawd
condition
and
(FL)
and nearly-lamellartime.
obey
the well-known
energy
per
cycle
Ti-74AI-
a TiAl-based
hold
Ti-24Al-I
aluminide-
INL)
INb
ally
condttrons
unities
ha\
and Ti-46AI-
Coffin-Manson that
I I Nh
TrlhAl-
the
behave effect
of