.
.
.
*
.
.."
274

-
!
2F
PIN
P
.'
MI
"
Tit
.
.
>
LOTTE
.
.
.....
!
11
-
L.HR
.
y
.
2..3.
.
..
2
.
'Storm
..
·
......
.
..
..
Vs
:::
I
w
FLEUR
.
W
L
.
3,"
.
.
1
.'
:.,.
5
-
'
.
'
2
:44
.
TI
.
.
.
- 1. IPA
+
4911
.
..
.....
"
1
,
4
.
..
*
..
-
-
1
...
TUM
,
..
9857
S-
ÜY.IN
7
!
...
*
"
1
'
'!
!
!
!
*
-
--*
-
:
..
.""',.
:''
i'.
i
--
-
'
.
';
'n
-11.1,
-.
..
.
1:21:
:
3
2
.
.
...
.
2
M
.
.'
'
.
.
II!!
!'
'
1
,
"",
.
.,!'!,.'
i'
..
i
L
'
WF i
i
XD!.
'
**
T
'
i
KU
1
lin
.
.
.
.
49,
'
1
**
.
*
.
..
W
30
(
M
Mi
.
*
"1.
27.1
. X
20
.
C
..."
"M'
j
ud
-"
"
.
.
.
l..'
ome
'
S
17.
.
.
1
.
20
-
...
it
M
.
' NON-
urdu
7:
.
LAVA
*
12
.
L
Ir
"
,
.
.
..
WY.
*+
1
.
2.
1
.
1
W..
.
.
.
.:
*
MARamos, a man
.
.
.
+
.
.
manos
en
*
Apm
7
10
.
104 W
A
1
.
+*
.
TI
-ORNL P
2355
.
A1
..!
Ary
...
.
.
$
TA
*
..
ht
'
t
EN
.
.
3
.
4
2
:
T
>
.
-
.
.
.
2.
W
.
i
F
*
* *
.
1
.
LO
.
.
ki
.
at
A
N.
!
16VY
UNH
.7
10.
.
.
W41
N
.
Hon
PUN
40.
KARY
':
way
Chuni
LT
Tiny
4,
LI
..
."
.
"
P.
USHALTUNA
$
.
1
.
.........
T
i
.
-..-...-
..
-
Y
.
...compe
·
.
I
As
:
•
650
[129
SG
i
.
125 1.4 LE
i
ki
.
C
AC
MICROCOPY RESOLUTION TEST CHART
NATIONAL BUREAU OF STANDARUS -1963
-, -------
16.1
-
--

SEP 27
ORNL-Q. 2355
CONf 660336-1
CFSTI PRICES
·
MA3.00 ; WN.65
OSNL
CLADDING AND DISPERSION FUEL DEVELOPMETT AT CRNL *
J. E. Cunningham and J. W. Ullmann
Oak Ridge National Laboratory
Oak Ridge, Tennessee
ciniai mieste santi e memorie meski atas believe in the content

RELEASED FOR ANNOUNCEMENT
IN NUCLEAR SCIENCE ABSTRACTS
con
LEGAL NOTICE
.
..-
-
This report was prepared as an account of Government sponsored work. Neither the United
States, nor the Commission, nor any person acung on behalf of the Commission:
A. Makes any warranty or representation, expressed or implied, with respect to the accu-
racy, completeness, or usefulness of the information contained in this report, or that the use
of any information, apparatus, method, or process disclosed in this report may not Infringe
privately owned rigbls; or
B. Assumes any liabilities with respect to the use of, or for damages ieswing from the
use of any information, apparatus, method, or process disclosed in this report.
As used in the above, "person acting on bebalf of the Commission" includ:8 any em-
ployce or contractor of the Commission, or employee of such contractor, to the extent that
such employee or contractor of the Commission, or employee of such contractor prepares,
disseminates, or provides access to, any information pursuant to his employment or contract
with the Commission, or his employment on to such contractor.
entiislamatwa na
* Research sponsored by the U.S. Atomic Energy Commission under
contract with the Union Carbide Corporation.
d i
si
.
- ORNL-AEC - OFFICIAL
,
INTRODUCTION
....
The presentation from Oak Ridge National Laboratory will be given in three
parts. The subject and speaker for each part is as follows: 1) Dispersion
Fuel Technology by J. E. Cunningham, 2) Fuel Reprocessing by J. W. Ullmann,
and 3) Fuel Cycle Economics and Radiation Effects in Cladding Materials by
D. A. Douglas.
· ORNS - AEC - OFFICIAL
-
--
002-Stainless Steel Cermet Fuel Experience at ORNL - J. E. Cunningham
miccamento consistence in umiwa na miaka minis na haitatis. ln elle
In reviewing the technology of the UO - tainless steel dispersion fuel, I
shall cor.fine my remarks mainly to irradiation experience accumulated over
the past 15 years and attempt to point up shortcomings of this iuel type for
application in FFTF.
As most of you know, the stainless steal-uranium dioxide dispersion fuel
technology for the Army Water Reactor Program was developed in the early
1950's. The product that evolved for startup of the SM-1 reactor at Fort
Belvoir, Virginia, was a brazed assembly of chin' plates. A representative
cross section of such a composite fuel plete is shown in Fig. 1 (LS-4278,
Y-25961) for reference. It consists mainly of a 20-mil-thick fuel-bearing
section with 5-mil cladding of type 304L stainless steel on each face to
give an overall plate thickness of 30 mils. The fuel is incorporated into
the fuel-bearing section in the form of 26 wt% or 19 vol % UO2. The
matrix material is type 302B stainless steel ponder, which contains 2.5 wt %
silicon.
r
minimalna kiselina imani nim
AT
These composite fuel plates were prepared by the conventional roll-bonding
technique. Most of the fragmentation and stringering of the oxide that is
apparent in Fig. 1 occurred during cold rolling (25% reduction) to final
thickness. These composite fuel plates of 1950 design performed quite well
in the 10-Mw thermal reactor at Fort Belvoir; in fact, they accummulated a
total power output of over 60,000 Mwd (10% greater than the expected design
11fetime of 15 Mwyr) before discharge at burnout. The operating conditions
were not very severe. At a power level of 10 MW, for instance, the heat flux
..
-
...
--'
.
:*
'
-
.
.
E
.ORNLAEC - OFFICIAL
ORNL - AEC - OFFICIAL
TEL
...
..
...--.---...
.
...
..
.
A
.
. .
.
.
.
....
.
.
.
.
was only 55,000 Btu nr-lt. The average surface temporature was 450°F,
while the maximum centerline temperature of the fuel was 6500F. The elements
were subjected to over 3000 thermal cyclay during startup and shutdown of
the reactor, because the reactor was used primarily as an operator-training
facility. The initial core loading accummulated a total reactivity lifetime
of 16.4 Mwyr. batore discharge. The average fuoi burnup in terms of depletion
of 2300 atoms was 26% or 1 x 1021 fissions/cc.
The effect of irradiation on dimensional stability and structural integrity
was checked by hot-cell examination of stationary fuel elements that had
been removed after various levels of exposure in the roactor. The first fuel
component was removed after 10.3 mwyr life, the second at the end of the
core life or 16.5 Mwyr, and the third after 19.5 Mwyr (higher exposure was
achieved by reinsertion in Core II). In-cell examination revealed the
following:
.
.
1) progressively greater tendency toward plate rippling
with increasing exposure. Maximum ripple amplitudes of
23, 33, and 45 mils were observed, respectively, for
10.5, 16.5, and 19.5 Mwyr exposures.
2) A maximum plate increase in thickness of 3 mils or 10%
occurred at the axial peak furnup position in the fuel
element with the greatest neutron exposure. The
burnup at this location was 62% depletion of 2350 atoms
or 2.2 x 1021 flasions/cc.
3) The frequency of intergranular cracks in the cladding
varied directly with burnup. In a few instances, cracking
was so severe that whole grains were removed at the
cladding surface.. Some transgranular cracking was noted
in the grain structure of the low-cobalt low-carbon
stainless steel cladding in the high burnup fuel element.
· QUNI - AEC - OFFICIAL
No evidence was found of matrix cracking nor sign of gross deterioration
in these dispersion fuel plates. Yet, swelling of the order of 10% did
occur under the modest operating conditions prevailing in the SM-1 reactor,
and such behavior must be factored into the design of the FFTF if the dis-
persion 18 used for the driver fuel.
W171130 - 13V – 1N1O
.
In 1962, we examined 34 disparsion fuel specimens contained in six Nak-
filled capsules that had been irradiated to relatively high burnup in the
ETR. These irradiation tests were initiated by BMI to evaluate various
parameters in connection with their program to develop an improved dis-
pers:on fuel for service in the Army SM-2 reactor. The cermet specimens
were clad with type 347 stainless steel and contained either to or UN
dispersed in type 347 stainless steel along with small but varying amounts
of burnable pois01, in the form of B,C, NbB2, and ZrBz. In addition, the
behavior of fused and hydrothermal oxides was compared. The highly en-
richeu fuel was incorporated in the fuel-bearing section to a nominal
composition of 26 and 38 wt% UO2 or 34 wt % UN.
of the 34 specimens examined, 11 showed failure. These specimens varied in
degree of failure from surface blistering to complete disintegration, as
shown in Fig. 2 (LS-13896, R-9043, R-3045). The six specimens with the high'
fuel loading operated at a surface temperature of 950°F, and all six failed.
Four of these were badly swollen and the other two completely disintegrated.
of the remaining five failed specimens, which contained 24 or 25 wt% UO,,
three were severely damaged and one developed a large blister over the fuel
region.
The micrograph in Fig. 3 (LS-8870, R-11235) shows the degree of swelling
noted ac the edge of a specimen loaded with 26 wt% UC12 and exposed to a.
fuel depletion of 74% of the 2350 atoms (2.9 x 1021 8188ions/ce) at 10000F.
Matrix cracking was observed toward the center of this specimen. A typical
picture of severe cracking is shown in Fig. 4 (L8-13897, R-11229). This
particular specimen contained 34 wt % UN, oporated at a peak temperature of
950°F, and achieved 63 at. % burnup.
ORNL - AEC - OFFICIAL
OONI - AC - OFFICIAL
W121110 - DIV-INIO .
Metallographic examination of the 23 undamaged specimens revealed no
evidence of matrix cracking or blistering. These specimens all contained
24.2 or 26 wt % 102, operated in the temperature region of 420 to 600°F, and
achieved burnups of 52 to 67% of the 2350 atoms (1.9 to 2.6 x 1021 fissions/cc).
No significant difference was noted between specimens prepared with spherical
(fuwed) or irregular-shapod (hyurothermal) vog partioles nor botwoon specimons
containing burnablo poison of different chemical form. The microstructure
11lustrated in Fig. 5 (18-9601, R-11306) 18 typica), for these specimens
and is quite similar in appearance to that found in the high burnup region
of the SM-1 fuel elements.
From mid-1959 to 1962, we worked on a cooperative program with APDA to
develop an improved Vorstainless steel fuol dispersion for use in Core B
of the Fermi Reactor. The scope of the program embodied 1) characterization
of spheroidal UO2 particles, 2) fabrication of composite plates, 3) feasibility
studies on nondestructive testing, 4) establishment oi suitable assembly
procedures, 5) measurement of fuel material mechanical properties, and 6)
irradiation testing.
Early in the development program, the concentration of fuel was limited to
27.5 vol % (34.5 wt%) VO2 in order to enhance radiation performance.
Spheroidal fuel particles is the 105 to 149-size range were chosen, because
we felt that this shape would minimize stress concentration and reduce
radiation damage in the fuel matrix. Type 347 stainless steel was selected
as the structural material because of its superior strength compared to
other conventional grades of austenitic steels in the 800 to 1000°F temp.
erature range.
The effect of cold deformation on the integrity and shape of the oxide in
the finished plate was investigated and the results are summarized in Fig. 6
(LS-7260, Photo 52670). Cracking of the oxide was noted at all reductions
investigated and stringering became pronounced at 20 to 30% reduction in
thickness; hence, we decided to hot toll the fuel plates to finish size
to minimize oxide fragmentation and stringering. During plate development,
ORNI - AEC - OFFICIAL
OINL - AEC -
We also noticed a wide variation in the behavior during hot working
of spheroldal 1o, particles procured from different vendors, as
illustrated in Fig. 7 (18-7021, Y-38004, Y-38989). Our characterization
studies showed that we nended some means to separate good from bad quai-
ity starting powder; hence, a new techãique based on solid embedment and
density was dovolopod to serve this purpose. A spooilication was also
written that allowed us to procure good quality spheroidal particles with
a high degree of confidence.
ORNL - A1C - OMFICIAL
Three instrumented capsules were irradiated in the MTR to assess the in-
reactor performance of the Fermi Core 8 fuel plate. Each capsule contained
two miniature plates, 2 x 0.6 x 0.116 in. The fuel-bearing section con-
tained 33 wt % spheroidal 10% af 105- to 1490 lı particle size, homogen-
eously dispersed in type 347 stainless steel as shown in Fig. 8 (18-6980,
Y-35413). Two thermocouples were attached to each specimen.
The nominal irradiation condition selected for in-reactor testing were
three different burnup levels - 10, 20, and 25% of the 2350 atoms - and
a surface temperatura of 925 to 950°7. These conditions were chosen on
the basis that Core B would be used to operate the Fermi reactor at a
maximum core thermal power of 270 MW. At this level, the calculated
throughput burnup would be 20.7% of the initial 2350 a tons; hence, our
burnup targets bracketed this level. Nominal fuel temperatures at the
reactor center would be 750°F at the plate surface and 970°F at the fuel
centerline. Hot spot and hot channel factors increased the centerline
temperature to a maximum of about 1040°F.
. .-
-
-
-
-
-
-
--
-
The first capsule was discharged after an estimated burnup of 9.5% of
the 2350 atoms. Subsequent measurement revealod, however, that the
actual fl8sion burnup was only 6.3% (average of two samples.) Conse-
quen'ily, an experience factor of 6.3/9.5 or 0.66 was applied in fixing
the discharge dates for the remaining capsules. On this basis, the
other two capsules were discharged after an estimated fuel depletion of
ORNL - AEC - OFFICIAL
ORNL - AEC - OFFICIAL
-
-
.
-.
16 and 26% of the 2350 atoms.
JINI - AC - OFFICIAL
Specimene 1 and 10, which were contained in capsule ORNL-MTR-64-4 were
unaffected by the irradiation. The burnup of 235U atoms was 6.3%. The
general appearance of spocimen 10 18 shown in Fig. 9 (LS-8898, R-4349).
All icur thermocouplo, romainod operational throughout tho tont and in-
d'icated that the surface temperature on those specimens ranged from 800
to 950°F. The appearance of the microstructure was as expected.
Specimen 6 from ORNL-NTR-46-2 showed severe damage, as illustrated in Fig.
10 (LS-8902, R-11567). Twr, full-penetration holes were noted in the test
plate. A major crack also developed at one edge of the specimen, as shown
in Fig. 11 (LS-13898, R-11569). Marked swelling was noted in specimen 5
located at the bottom of the capsule. The appearance of specimen 5 in
transverse section 18 depicted in Fig. 12 (18-13899, R-13091). Gross
swelling (ale -13%) and matrix cracking are apparent. In this specimen
the surface temperature ranged between 850 and 1150°F throughout the life
of test and the measured vurnup was 29% of the su atoms.
Specimens 8 and 9 in the remaining capsule showed obvious swelling after
a burnup of 33% of the 2350 atoms. This behavior 18 illustrated in Fig.
13 (LS-13903, B-14325) which shows specimen 9 in transverse section.
Specimen 9 increased 6% in volwe. A longitudinal section of specimen 8,
which increased 27% in thickness is shown in Fig. 14 (LS-13901, R-14261).
Temperature ranged from 950 to 1050°F during test; the average temperature
was 1000°F.
These irradiation test results indicate that the temperature-burnup
limitation of the improved stainless steel-U02 cermet fuel for Fermi
Core B was definitely exceeded. Moreover, it should be noted that the
specimen size was relatively small, 80 one would expect better performance
due to the restraint offered by the cladding and frame material. In
addition, control of particle shape and distribution of fuel appeared to
offer only marginal improvement in performance.
Tissu-doi-indu
· OANL - AEC - OFFICIAL
During the development of the Fermi Core B fuel element, several advances
were made in the developrent of nondestructive testing techniques to ensure
compliance with specifications and as-manufactured product reliability.
Among the developments were
ONNI AEC - OFFICIAL
1) an ultransonso toonnique that is capable of detecting
core-cladding interface nonbond areas 1/8 in. diameter
or larger,
2) an eddy-current technique capable of measuring the fuel
plate thickness to within an accuracy of * I mil,
.
3) a radiographic technique to detect UO2 concentration in-
homogeneities in excess of the specified = 5% tolerance,
4)
a spacing measuring device, based on recently improved
eddy-current theory, that moasures coplant-channel gaps
between plates to + 0.5' mil, and
methods for characterization of UO, powder so that par-
ticles of the desired shape and integrity can be pro-
oured from the vendors with a high degree of confidence
that the material is of high quality.
An analysis of pertinent irradiation data on the performance of 10,-stainless .
steel dispersions has been compiled at ORNL. These data are plotted in
Fig. 15 (ORNL-LR-DWG-75068R3). It should be noted, however, that the temp-
erature points plotted in this figure are based on estimated values since
only limited data are available on actual surface temperature measurements
during irradiation. The curve indicates that to achieve a burnup of 2 x 10%
fissions/oc the maximum surface temperature of the fuel should be less than
800°F. At a surface temperature of 1200°F, the maximum burnup that can be
achieved bolore uncontrolled swelling occurs 18 about 0.8 x 1024 1188ions/cc.
1
ORRI - AEC - OFFICIAL
DRNI ~ AEC - OFFICIAL
-..-.
-
XML
Ideally, a dispersion fuel should consist of components that are in equi-
librium with one another as well as with their environment at all times.
Chemical stability of the components, for instance, must be maintained in
fabrication and during the lifetime of the fuel in the reactor. Plutonia
and urania exhibit notable differences with rogard to phase stability.
Uranium dioxide is the oxide of lowest oxide content in the uranium-oxygen
system whereas PuO2 is the highest oxide in the plutonium-oxygen system.
Silicon, a tramp constituent in stainless steel, will reduce Puoz.
Finally, I would like to state that in my considered opinion, the Puog-
stainless steel dispersion fuel is a questionable fuel concept for FFTF
operation at 1200°F. At best its development to provide adequate service
will be an expensive and uncertain proposition. Radiation-induced
swelling of Puo, and severe thermal stress under condition of high power
density are likely to lead to premature failure of the potentially em-
brittled stainless steel matrix and cladding. It is true that certain
measures can be taken to improve performance at 1200°F, such as built-in
void space to accommodate fission gas and reduce swelling. Unfortunately,
no one has come up with a practical way of achieving this objective
despite the fact that its effect on performance has been suggested for
some time. Other parameters that potentially influence or upgrade per-
formance are: 1) higher strength matrix and cladding material, 2) lower
concentration of the f1881le phase, and 3) lower temperature. Yet when
all these factors are considered, the Pu0g-stainless steel carnet fuel
concept appears marginal for application in FFTT at temperatures of
approximately 1200°F.
ORNI - AEC - OFFICIAL
:: ORNL - AEC - OFFICIAL
ORNI -ALC - OFFICIAL
: A, Bibliography of References on trounicom Dioxide-Stainless Steel
Dispersion Fuel Technology
1. M. J. Feldman, R. J. Boavar, and J. E. Cunningham, "Radiation
Damage to Solid Fuel Elements - The Effect of particle Size
on the Mechanical Behavior of Irradiated Stainless Steel-102
Fuel Elements," TID-7526, Part 3, (February 1957).
2. R. J. Beaver, R. C. Waugh, and C. F. Leitten, Jr., Specifications
for Army Package Power Reactor Juel and Control Rod Components,
ORNL-2225, (July 24, 1957).

3. R. J. Beaver et al, Investigation of Factors Affecting Sensitiza-
tion of Army Package Power Reactor Fuel Elements, ORNL-2302
(Sept. 18, 1957).
4. 'J. E. Cunningham et al., "Fuel Dispersions in Stainless Steel
Components for Power Reactors," Fuel Element Conference, Paris,
November 18-23, 1957, T1-75146, Book I, PP. 273-268 (March 1958).
5. J. E. Cunningham and R. J. Beaver, "APPR Fuel Technology," Pro-
ceedings, UN International Conference on Peaceful Uses of Atomic
Pnergy, Second Geneva, Vol 6, p. 521 (1958)
ATA
.6. v. 0. Haynes, F. H. Neill, and I. D. Schaffer, Summary of 102,
U
ORNL-CF-58-2-71 (March 18, 1998).
7. J. E. Cunningham and R. J. Beaver, "Stainless Steel-Uranium Dioxide
Fuel Conponents for the APPR," Nuclear Metallurgy V, pp. 29-40,
Series No. 7, AIME-IMD Special Report (1958).
-
-
--
-
-
-
lam
8. J. E. Cunningham et al, Specificacions and Fabrication Frocedures
for APPR-1 Core II Stationary Fuel Elements, ORNL-2649 (Jan. 1959).
iner
9. A. E. Richt, Pontirradiation Fxomination of APPR Fuel. Elcment Irra.
diation Program Specimene, ORNL-CF-59-3-33 (Mirch 9, 1959).
10. J. R. Weir, A Failure Analysis for the Low-Temperature Performance
of Dispersion Fuel Elements, ORA L-2902 (Mey 27, 1960)
Voitur
11. J. H. Cherubini, R. J. Beaver, ond C. F. Leitten, Jr., Fabrication
• Development of 102-Stainless Steel Composite Plates for Core B of
the Earico Fermi Fast Breeder Reactor, ORNIM GOT7 (April 4, 1961).

e
..
.
..
ORNL - AEC - OFFICIAL
..
ORNI - AEC - OFFICIAL
.
......
ORNI - AIC - OFFICIAL
12. J. E. Cunningham, R. J. Beaver, and A. C. Waugh, "Dispersion in
Metals, Uranium Dioxide: Properties and Nuclear Applications
Ed:. by J. Belle, Naval Reactors, Division of Reactor Development,
USAEC, Washington, (September 1961).
13. R. W. McClung, Feasibility Studies for the Nondestructive Testing
of the Enrico Fermd Poactor Core Vol Element, ORPL-3221,
(December 21, 1961).

lk. R. J. Beaver, C. F. Leitten, Jr., and J. L. English, An Investiga-
tion of the Corrosion Reoistince of Brazing Alloys for Austenitic
Stainless Steel Fucl Elementi for Service in 565 F Pressurized
Water, ORNL-2834 (March 29, 1962).

15. J. 8. Cherubini and S. Peterson, A Technique for the Quantitative
Characterization of Dispersions, ORNI-TM-446 (February 28, 1963).

16. Army Reactors Program Annual Progress Report for Period Ending
October 31, 1962, ORNL-3386 (April 2, 1963).
17 ; R. J. Beaver and C. F. Leitten, Jr., A Survey of Corrosion of
Martensitic and Ferritic Staj.nless Steels in Pressurized Water,
ORNL-TM-539 (July 16, 1963).
18. R. G. Donnelly, W. C. Thurber', And Q. M. Slaughter, Development
of Fabrication Procedures for Corc B Friel Elements for the Enrico
Fermi Fast Brceder Reactor, CANL-3475 (July 1961).
19. . W. C. Thurber et al, Irradiation Testine of Fuel for Core B of
the Enrico Ferm 1. Fast Breeder Reactor, ORNL-3709 (November, 1954).
20. A. J. Taylor et ailey Characterization of Spheroidal UO2 Particles
and Studies of Fabrication Variables for Corc B Fuel Plates of
the Enrico Fermi Fast Breeder Reactor, ORNL-3645, (August 1964).
21. v. 0. Haynes and A. E. Richt, Preirradiation Data for the Fuel
Specimens for the Army PM Fuel Experiment in the ORK Preseurized
Water Loca, TORNL-TM in process of publication).

5. Blbliography of References on Irradiation Damage of Stainless Steel
in W. R. Martin ard J. R. Weir, "Effect of Postirradiation Heat Treat-
ment on the elevated Temperature Erbrittlement of Irradiated
Stainless Steel," Nature, 202 (4936), 997 (June 1964).
----***
.com **** -
------- wm.com.
...
.....
-------
powerpoint prennent pouw program
181)1310- 33V.INIO .
· ORNL - AEC - OFFICIAL
2
W. R. Martin and J. R. Wcir, "The Effect of Irradiation Temperature
on the Postirradiation Stress-Stirain Behavior of Stainless Steel,"
Pp. 251-268, Flow and Fracture of Metals and Alloys in Nuclear
Environmento, Special Technical Publication No. 380, American
Society for Testing Materials, Philadelphia, Pa., (1965).
?60-33W-ME

.
J. 1. Venard, C. R. Kennedy, and J. R. Weir, Effect of Irradiation
on the Mechanical properties of Stainless Steel at 750 C Under
Constant Stross Rate Conditione, ORNL-TM-1216 September 1965).

4. W. R. Martin and J. R. Weir, Effect of Irradiation Temperature on
tnc Postirradiation Strc88-Strain Behavior of Stainless Steel,
ORNL-IM-906 (October 1964).

: 5.
W. R. Martin and J. A. Weir, Influence of Grain Size on the Irra-
diation Embrittlement of Statnless Steel E! Elevated Temperaturas,
ORNI-TM-1043 (March 1965).
-
-
-
-
-
-
--
6. 'W. R. Martin and J. R. Weir, "Influence of Preirradiation Heat
Treatment on the Postirradiation Ductility of Stainless Steel," .
· Nucl. Appl. 1, pp. 478-483 (October 1965).
-
-
-
-
-
-
.
7. W. R. Martin, J. R. Weir, and R. E. McDonald, "Irradiation En-
brittlement of Low-Boron Type 304 Stainless Steel," Nature, 208
(5005), pp. 73-74, (October 2, 1965).
8. J. T. Venard and J. R. Weir) Efect of Irradletion on the stress...
Rupture Characteristics of a 20%C 2599 NI Niobium-Stabilized
Stainless Steel, ORNI-IM-1359 (Foaruary 1966).

..
....
.-
.-.-.-
.-.-.....---
-
IV2133
OINI - A&C - OFFICIAL
NI - AEC - OFFICIAL
FFICIAL
OINLON
OIN - AEC
"
3:48-53459


|
4
|
พ
t, ระนง ! ;
"
"
"
"
" " "
" .. 4 . '
(4ษ"
+
*
1
"
":
“ (AH1: :
11
-
4
(ชม :
1
.
.
พบป"
:
"
"
"
"
?" ""
“
!" + " "
เ เ
*
เ
!
1
"
-
---- -
-------
ระยะ ๆ
•
•
• .
.
""
--
-
-0.035 INCHES
[ +0ox
บางนาม

"TITV。
{ " d
"
.
.
1.
"
.
1
一件事是​,
14.
:
:
qi '''''
重
​**
*
Myw世
​PS
.
,
「.
了
​|
。
|
,
「
.
11
..
,
小
​TIT":
11
,
.
"
-
事事​,裡面
​ups.
中的
​+1
i
-
.
人
​.
.
,
hr: I
°k
14
-
.
「.
”
,
$
.
.
,
.
字
​:
…….
"
{
.
:",
"
w
:
;
:
/
事
​|
,

才
​。
。
:傅it ,4 ,
..
心​,
1
、
]
Air tttt",
,
.
"ti
",
.t
TEM "Tell'
FLASH,
.'
ETE
:
1
}
可是​,
「.
'''
'
',
..
一一一一一一一
​l
]
WHI LL ' i',
_ _
_11
|
_
| ,
MIT
::
|
Pa
|
11.
11 ::
的
​。
”
件事
​ail
,連业
​:
Tril
II,
I
是
​」
"T
G
il'
,
:
The ses.
m let M
i lip 地非
​J'
lift,
|
|
"
r
--
工作​;
W
。



|
是一生一世
​書​。
-

S
: $
*
1.
.
Whe
on
WILL
I
N
M
.
0.035 INCHES
W 100X

.
1
.
"
.
TA
- L.
LEAN
.
I
FURI
.
A
.
'
. .
.
:..
.
1
IN T
E
:
-0.01 rotr
11 260
In In T. INT
UNCLASSIFIED
PHOTO 52670

2%


u!
1
.
......,
k...
t
.
ing
.
f
5%
10
%


-
-
20%
30%
i 2003 EEELL!!UELLO
Effect of Total Cold Reduction on UO2 Porticle Geometry (Batch A-534)
'


O
•

-0.07 INCHES
TA 50x Toy

Si..
.
-
*
*
*
15-
To-
-0.07 INCHES -
TA 50X100
ML XOS v
- SIHONI 200
-

*
::
,
:41:3.
"","f":
*_
-
1
.
..''
....
i.
':
T
.
_
.
T
.
.
1
.
Tri....
!
:
I lia',
},
重
​自主​,
中​:
T.
:
::
:
,,
如
​;
; all ,
,
,
..
"
"
..
TEL:
民产​,
但上
​,
上
​,
F115
" "
""
实
​中中中中中學
​他
​:
三
​:
品
​Pi
武
​。
"
,
"
控方
​上
​F10
;
,
:
:=
,,,
| .i
we
EPS
LTE
::
=
17
|
|
:
TEL
:
+
.…
法
​.
,
1:
:
.
|
::
y
:
型
​。
:
,
:
.
| ii
十一​.
,
4
事
​十​.
.
”
其他
​:::
-
。
-
AM
非
​基
​1.
,
A
,
.
,
114
意
​中
​4
,
、
事
​,
.
.
}
,
业​;
.
.
.
-
十
​.
-
::
}
「.
v出了
​手作​,
HT
重新
​,,
。
.
·
4"
都
​地-
​書T4
年​..
,
"
TRIP..
;
|
..
1
.
.
.
有
​.
.
.
-
|
--
"
.
完
​-
:
:
-
,
1
4
「是是
​,
是到​:
er,
加中
​曾
​多
​了​。
1.
.
“E,
,
「
大
​TH_
.….
。
.
:
...
..
..
.
中​。
*
一​. 7
-
.
,
IN'
.
.
.
.
'”
·”
-
.
”
:
Lill
·广e,
*.
| :
.
,
14
多​。
,其
​是了​,
十
​.
。
身亡
​T
..
中國
​:
T",
A:
點
​T-
-
4"
.
:
..
一​,
具
​..
4
,
,
”
“
-
种​”
rt
1F='。
1
*
.
「
中北
​心​」.
.
.
能
​-
賽
​--
:
y
:
.
一​:
…
學會​!
高强了
​|
|
务
​#
*
:
;
.
...
4
.
:
..
--
4
TS
LET
f.
了十年​,
「,
」
|爭​。
。
中​。
41
*
工作
​:
HTT
广
​到了​,
子
​,
*
注​:
|
5:41
.
...
.;
* 14:
HTT
17导​。
4
:
·,
。
量
​,
1.
19 ::
:
::
,
*2
1。
1
*
:
“.txt-
|
-
A.,
11.
-
件是​:1.
4
,
|
|
,
1.
il
:51
,
多
​,
:
事Tale
的
​:
的
​序
​.
:
左
​.
了​,
.
"
:
事事
​:
"
4
THE
。
:
九址​:
E
,
到
​.
::
11
.
:
地址​:
。
|
,
:
學子​,
.
.
.….
A
:
重量
​|| ' llll
好​,
TTY TAL,'',
|
|
| P
1.
|
33s.
-:
建军
​“
1.
*
评​”
二
​n
幫
​子​,
T
TTN
.
,
“行​!
*
品
​·
-
中​。
1. “T,
附​..
.
.
。
*
--
.
..
.
ite
ty;
Ps..
,
11
就
​-
|
年
​:,
“一
​th:
:
: :
..::
斯
​:
以
​::
|
“是的
​',
-
1"
,
1
进进1
「
,,
,
台中​.
生​:
:
#
'
..…
'
:
*
左
​等等​。
,
「是​,
,
亡
​ww444.}
3机​{
我rjet v+i ^
4 HPH
ENT
T
*
科比
​**
下
​"
:
.
.
中
​*
,
、
此​,
宁​:广告
​..
1# -
" us
FFX进程
​曲
​*
L
5
:
44
「*
_y
,
一​、
15
--
::,
、
..
''''
'
T;,
tar
都
​景​:
上了​,
:
:
:
:
:
来说​,
英
​.
-
。
E」
.
y
,
,,
Fab14
"
*
*
,
不一​,
程
​,
:
5i..
SE-INES.TAIWAN/mm - Mom
BWIFILM
1位
​TELLECT,
“
.
.
:
:
::
。
.
是
​車上
​「
全
​|-
"
",
''.
****
斗
​。
LA
:
"
出
​|
1.1
「
好
​”
.
Yes,
***
,
null,
ts"
:
Air
_
|
.
| Fi
A.
,
L
-
-
.
..
...
"
雄​!
,
.
11.1
下去​..
.
他一
​| 1分 ​4
H
it i;
。
了
​.
四
​...
.
...
,
注​”,
{
| ::..
...”
",
ht
,
ME
":/
' sty
,
11.11
"
·
**.116
1
F
比
​.il
, T
:
」
物
​「
人
​牠
​| PAR
l
i
'il
|||
「,「ALWl
*
|
“
青​,471
***
:
. …,
" , AT A
d
y' (
TTA I'v1
"
--
" tit; .
.
1,
:
u' y! JAPA
: LINENTENT :;
NT":{"
i
: :
:
均​」
…
的​。
。
-
PTT.::
iTIID=
11
.
|
1
:
2013
.
.
.
“
-
tit;
44
.
..
.
AL.
,
Hell'
,
.
:
* "
|
12:
.
由​。
r
4
1
"th
”
中国
​.
,11,
我
​"
人事争
​(
ii
出一
​,

**
*
**
,
:::
# 44 14:
量
​Luil:
EP44,"Til :
* *
子和式​:
AI,
。
把
​.
..:''x'
「
中
​”
.
中部
​。
....
:
是
​...
:
找矿中
​在​'
Tag":
:.
:'”。
.
?
:'
', '
:
:单
​TL
:
:
就是​:
“
“
.
-
..
三
​|
-
H律
​..
i
..
…
”
17岁
​.
“
.
..
产量​:
-
-
f
=
作者
​.
.
al.. |
w
,
“
、
号​:
社
​是善于
​"
.
ht
.
..
…..
东
​t
.
,
.
HT,
.
.
1
“
人物​:
+
生
​,
4F
|||
-
率​。
1,
*
-
“中
​「
此
​..
,
成
​,
|
“我
​等等
​-
队
​业
​1
有​,
「中
​:
:
Em
林​:
It
重量
​|
|
计
​.
.
-
|
|
手​,
,
。
{
未生
​事
​*
。
-
:
AL,
|f
事​。
中
​生
​1
"
。
*
*
作
​M.
·
.
:
带
​在
​-
「
.
{
,
,
.
--
事-
​W
「.
-
1
主
​.
T
-.
,
,,
ht
.
:
4:
作者
​:
到了
​:::
.
.
.
-
..
.
-
。
-
“
子上
​..
中
​.
- Tra
.
.
A:
11.
1
|
F
!
of
r
74
"
国​!
了​,
中​:
**
LTI
11-
AL),
-
Hi,
I
'
的
​.
、
神​..
-..:
.
「
是
​.
中
​作者
​:
::
hi,
!
,
.
于中
​,
往事
​,
事
​h
.
}
A
相s.
'
.
'
,
--
5.
| 49
:
*
--
::
「
1
深
​..
***
};
:
三
​了了​。
.
it's
clar
.
14...
..
“
·杰一
​,
1
/
1F.,
-
业​,
产
​21
.
18:
i
F
.
“少
​..
”
..
.
“
.
.
「
11
中
​Lil',
.
..
我
​11
,
音
​上​:
:
,
,
,
.
Th,法​:
。
“
了
​--
-
Air
”,
.
三
​.
「
.
| ult
::
所以​,
,
但​,
.
-
*
,
.
,
是​,
.
-
;
“
“
.
-
| 11
。
三​”事
​1
:
.
-
|
-
r
-
1.
.
事
​| 重量
​,
”
,
,
*
14.
"
1
中
​:
4
.1
:
中​"
波
​喜
​学
​,
,
,
产
​中主
​-
“
|重要的是
​。
中洲
​!
if
PTT.
IL.
T" 1" |--
中
​.
::
' |/ AM
:
-
斯
​事
​;
II
.”
|
ETS
」,
|
|- |
量
​|
.
1
=-=
.
|
产
​女
​:
".
::
=
时
​IT
|
l
*
Line My出​, {'t再利用
​-
fr
.
ac.kr 上
​,
T''' MP
中
​h
,
.
.
HTTY, Wu
「
」
:
.
注​:
'
',
, T
PSV-14《LAURIAL.
-
_
-"
4_T1"id"P"
:
-
-
!
11.12.
34
" F
14
1
,
xt:
r

=
一个
​.
*
“不​,”
.
”
=
_
=
*
/
.
-
-
-
:
:
FRI le"
:
重生
​:
”
:
|
:,
#
--|-
111
.TW
*,
5
.PTT
1.
Tri",
*
此卡带 ​lll. li
||
|
-
中山
​A: 1
.
FF'
.
..
生与
​.
;
A1
:n ::
:
:
.
.
。
了
​A:
。
-
Fw
"""
{iffn"
,
·日
​:
:
:
/
fi
主
​」
as "
-
-
4
*
多的
​1-
14
".
An!
“
..
:
:P :
.
1'
,
T:
:::,
T
TP:
·
…
:
L
' |
4h.
.
F475
一
​:
作​,
p.
| 4
岁的
​|
|
|
A
:
.
.
Air
-
FF
百事上​,
A. THE
Fla
Are ::
-
::
"
'''
''
''Biiii
sh:
9
.
7"先
​"
|
1
1
.生
​主
​了​,
-
...
2-11
r
?
| 国​”
“Lull
是
​;
"f
Kith
"
"
,
"
的
​,,,
h
":
.…..
”
,,,,,
,
事
​。
论
​中
​:
..
5,
中
​.
-
11.
:
"
s
-
.
.
:
-
“
L
1
.
,
「
-
….
*
T
土
​-
,
..
.
中吃​:
.
:,
.
::
e
:
10
:
11,
| F事人
​1中
​iri,
,
"
.
h业有
​.
,
,
""=
,
于是
​,
|
「
.
.
.
:
华中​。
:
.
:
《
中
​.
.
.
5
艺
​”
于
​'
k.
.
-
*A
/
「
."
是
​|
·“1..
.
.
期
​」
'''
; ;
--
-
-
「」
「-
"
了
​!
i"
*
,
:
, ::
ast
"
上
​,
:
13:
*
L
,
"1" TH-
-
“你​”
.
以上
​本事
​,本書​,
,
%,经典到​,
'
'
'',
F
'
Ti
事
​-
--
“.
「WAN
.
-
= rel
注y
:
SE,
拿着
​P
"
eak:
-
"4FTV....
:
-
A
“
...“
RT.i
「我
​|
-
"了​," Ill
中
​。
出
​「
station,
'
'
.
|
* *
由
​身
​--
juic., #
事​。
1
=
r'
.
能力​:1.
L
I'
L
( 14:
:“是的 ​, 生​:“ 中
​15
AME24
|
|
|
|
:
:
:
十一书​,
.…
。
.……skha St MA1出
​4
当
​-
*
“
了​:
- ALL"
•
'-
·上
​th:
levail
"
:
:
Th,
.
,
MHW
.
}
,
,
Lin
;让
​,
-
-
實
​事
​=
,
所​..”
--11fner-卡七​:
r.
1
.
.
1. ,
士
​INEN)
MLSc h, 1:
-
"
*
***
11:
*
民
​11
"
"
,"
一
​書
​***
*
-
。
学
​-
*
“
.
“
…
一
​::
::
- ii
作
​1
”
能量​,
“
-
,
ler
--
-
.
得了
​,
“
T'-'...-;
|
.
1.
-
“.
1
-
手工
​書
​T
4式-
​..
.
會
​her..
,
身音​,也是
​1:
在手里有​?
·j***
中
​我
​:
14:
29plum
L
;
H
|
主
​.
.
st.
..
中
​“…
いかが​?
量​。”
工
​”
活
​:
在上
​E
=
1
事事​,
:
王​,
"
中部​:
.
:
.
..
”
=
:
y
41
=
.
1,
if
=
..
-
14
"|
"
=
.
-
1,
上了​,
:
「
,
:
1
.
更司
​is
在
​二十
​h
, : ,
::::
. .
:,
:
,
中
​出​;
「有了​」
其實​,
,.
.
.
.
..
6T
::
::
1:
13:
tvie H
-
出​!
1
'
,
重​,
IT'
!
了
​All R::
"
,
"+"
"""'il T
*
i .
* m: him, Jil.i
1. 說
​“
:
是
​..
1.
.」
| try
。
.
PTT Web
“
那
​,
= hk
"
i'
作用​,
,
r
'
|
|
|
ttt
”
La,
,
":""
.
重量
​'
,'',' J
.
1'
, .'"
1
,
1,
1
*
」
In 1
「
..
.
-
N
S
WEET
::
:
...*
::TG!! :::
:....
.
::
:
::
:
:
:,其他
​:
:
:
"h
·
2017
-
*
H" }
“
中
​-
Th,
"
I'a ,
-
-
*
W
*** -
-
以上
​事
​|
19
2、
Airitic
,
中心​''' ' '
, "sql
"
""
:
:
:.
|
*
.
.
Mrs
.." 我
​第
​1
.
1.
Atmai
l
js lily
y m
|
身上​,
一身​」 畢書
​」
HY
29
st", "... 中
​4
:-::-
.
A
"
I+ THE
11 引产
​-「
H
T
-
",
|-
"",
:::
轉
​,
,,
:
青
​,
2017
.
!
::..
.,
, L
,
「
'-'
, '
|
重
​工
​1
,1
*
.…
是非常小事​,
"
",
.'
…'
.
*;.
.
..
,
.
「
{"
:
"W" Hilly
-
Pow业中
​.
,
一​:
F
TTA |
AI
~
..
|| ::":"HTTL:"ht in
.、
对
​1
“
Li Yu”
{
“
THE
A
v
山
​WHILI
.
{}
| 4 11
,
TEL:
's HiP
1
·
.
y
/.
如​:
T
W
'''''':
件​,
'
中​:
rt,
!
**
*
”
Airi
,
47.
中港Tu」
#,
,
*以上
​.
:
”
'
l
-1 1" il
3
4.'
itory h业
​'
Fals
11月 ​-
1
..
.
L
/
TE
-
|
上一代​,
了
​.
"
,
“
,
可
​-
#
1.
ht:
HTM”
*
音量
​”
.
,
Eg:
,
,
:
ET
。
:
量
​,
:
作者
​,
it .
重​。
上
​「
.
.
",
.
.
1
..
香
​中
​-
..
,
"
-
.
{
,
"
,
.
.
14
.
七分
​.
:
..
.
重量​:
1
「死了​,
-
|
.
…
.
|
14:
.
11:1,"ET
|
.
|
%
“;
14:
“SHI
重量
​"
量
​}
}
1.]
}
,
Top
.
i
LE
,
*fil
.
「
有​',
.
中的一种​,
L
多
​重量
​「
"
「
.
,
.
.
..
萬事
​事
​. ..
一把
​|
-
:
..
事
​,
平臺
​"
.
材​,
基
​1。
工作​,
|
jiYA
|
中
​li,
|
1
,
..
1
「
島
​-
-

.
. 1
,
۸
۲ .
و
: وان
."
:
۲۱
. هو
''
|
4
|
I
*
ادامه
.
.
" "
.
"
نیا
ا
و
و
و
| |
| |
'
!
"
و ..
و
. ا : ا وا
: : ا ب
'
و ممه
ا
اد
زاء
"
..
" ,".
","ا
"
-
.
. .
!
-
.. وز!
:ال
دستیابی
"
.
.
.
.
.
. .
1
م
د
عطعوس عمده و جامعه
ساوه همه ما
*
.. مد
ماه
"
.
الطما -
و
.
.
.
.
*
.
..
1
ل
.
.
د
.
'
: ال
سبد.... دهد. ..
.
.
...... هم بد...
ء
،
. سم
-- ا
"
،
|
"
عموما . سم ، ارده
*
۳-
به '
ه ست؟
ار
*
سرو و
به ده .نقشه تفسه مند
. 4
.
ا
. ع
.
1
ا
و
.
/
.
*۶۰: "
۰
۱۱ ۹ ۱
''
,'
'
و
"
.
.
.
*
د شده
اما
.:
:
؟
..
. نم
!
و
ماشین
ادم لحاله ...M
و العبارات
المي ا
امام -
اسال اللهم زد حال
ک
و ا ا
ا :
فرایند :: ,
مساحة الاناناس
ما ب اشد. با
.
... ...
ار
+
A
2.
1
:
ا
ا
ا
و له
ادامه به
مطب متوجه شد. » .
همه، ...، . .
.
-
1 لا
"
1
.
هر
+
ا
ز
:
: .
11..
."
م
د شهید
.
ا دم
:
م. ا"
''
. .!''
''ما می
11
,
13
."
عمده که البته تالیاں بجا دیا
ماهی
ندرلبورونه - دان ... من ل م .
. . .. . -، حه . .
- دی,
"
*
-
التداوه
!
!
"
.
. .
.
"
.
ا ا
ا
د
:
ا نا : .. '
'
یا
.
.
.
1
:
:
:
ن
'
.
.
جد، اس
.
'
'
سد
خه :=
وم
+الم
-
+
،و ...
م ...
کد
:
:
.ما
گل
..
ج
:
.
. .
.
-
+
=
*
-
. .
.
1.
.
. .:
:.:"
.
*
*
-
*
"
جمعه هم معهد
1
د
.
.
وه :
و
R
.
؟ و :
ا
ن
. .
.
ستصبهانی معمول
ب دهید
، د ای
، .
و ده و
"
لا -
عل
-
اقلا
د
م
"**
* *
*
.. ..اهههه
|
*
د
*
1
:
13 -2-
*
اها"
اومید که
"
.
در
د
م ل
ه ء ا
د
ل = امام
.
الجمل
کے
و
!
ر
ا
.
"
:
,
.
:
-
1
.
أ-
,
',
*
:حجم انم معلم محمد عوض
*
*
ا
ي:
.
-
'ز
:
*
.
|
* .
*
*
عبد
* *
هههه ا ...
*
.
ا
.' 1
.
:
.
الرحمن
:
:
الان :۱
,
. .
,
.
غم تو
.
.
ا
'
'
امام
!"
.''
.
مردم و به
"
65
,اء، :
. . ب
.
:
:
.
:
من به لانه پر
.
.
ه
,
الان
:
.
د
"
""
. 11
و هنا
:
1
لحية خ
و
'
'
.
امام
:
:
*
.
... و
به
۱۰
,
،
".
,'
د ومین
3
به
. .
.
نه، هم ته...
... ، چه .
.
Hi:
تنها به مدت شد
من 4
. . مانند
منانا
الهدا
لما لها
د. نه ای
.
:
به
..
"
بال
ماهه اولا ۴ة
.ا
۔
.اما
:
ا
.
..
تر .
. . .
"
ا
أ
. .
.
. د
.
. .
"
"
-
:
فهمد.،
، الم..
,
:.. :: . "
.
و به سه
--ل، .
.
دم ده .. نه ...
م
. م
. م .
ا .
ا
س
د
:
- . - ..-.
.. . - .علی ...
.
* کی
:...
ملي
.
"
.
.
|
با
نشا + گا
ن یا
، ۰
نی
*
را
به •
به ی
الم
4
"
فيه
د
. '
1
**
همه
ما الان
ا
"
.
ای
'
'
'
،الالا
با ما
ل ا
:
"
به )
!.......
*
--
-
.
.
- - .
ت ا
والا
"
* شاخه
-
" "
.
:
.
:
رااا
'
و
را '
'
دان
:
ا
بدا""""
'
'
:
'
'
ا ا دروا"
کیا
'
||
I
ها
"
"
:
"
د
-
*
و
نه
\
:
ای *
"
"
جيء وخي" ,
ب
۴
- موسع
, ها
المهم
دم همه
اور کیا
ام
ا
م
ا
.. .... سب
ضل
"
.
*
*
اس
انه وممنوم
ل *
ا
*
1
E م
.
لا ،
"
" من
.
. بل
: - اس
لی
نام برد. ای عراء.
امامه ۹۰
- ا1
۰
.
دعه يار: :
لاننا لم و د .
.. , ۱۱ - ، -
ع
ا
2
م
ة
ا .
1
. .
د
، وه وه ."
.
.
-
...
"
.
یا
.
م هه
م
:
.
:
'
"
:
..
:: 1 41,
. " .
"
ردای مهریه
می
دهد به
..
{
م
,
,
ارد
: ..
:
راه
،
.
اد
.
.
-
-
یا
: له:..
ا
ن
ما بوده
و
با ...
.
. .
. .
= * *
|
"
:
بعد
سجنه بعدها
هر ...
رعد و
.
لة
ل
ا
لا
مهم
انا
و
,
مواقع
:
1
*
1
.
::
ا
*
|
ب او
-
با
-
پ
"
"
د
.
.
.
نم
ا
را
اما
.
امیرشة لمر
.
:
1
ا
:
ا
:
:
:
ابر -
.
نه، همصد-خ- مي
:
, اند
.
"
:
او "
ء
ا
|
'ل
*
: 3
.
.
لمية
* *
، ای :: برهان
'
لا "
الله"
ز
،ن .1
*
.
ام
.
ہی ادا
. ه
*,
*
-
. ب
: دارد
:
::
الا اود
من "
.
"
"
م
"
..::
"
" .
'1
.. :
.
:
اج
-
.
.. .
. .
.
به
.::
و
.
با ولا ألم ''.
1
و
:
. =
:
.
:
..
:
: :
*
:
سیاست
.
-
4 ای
انتهم
-.
ه
ا و
*
از |
- -
منهم من يدي الله عنه فيه، له ساند مدیر , مل
جل ..
المهم .
کن
:
کم
ع انر
ربی
، و
.. :: د
.
"
ا
۹-
..
اسی
..
.
:
و
ف
-
از
-
انور
ارا
:
ا
: . . ا:
نو
.:
:: د . د
.IR د
به
ا لان
| '
و ما
' ۹۶4 :"
م
.
"
.
.
''
.
.
"
,
,
,
,
,
i,
"
"
ا
ا
ا
ا
ا
ا
ا
ا
.
''
ادهم
""
|
ا
ا
ا ه
ا ا
ا
وی پر
"
ا
.
.
.
.
ا
ا ا
ا
ا
اااا
'
،
ا
ا ، و
و
ا
ا
. . .
. . .
ا
ا
. .!
th"
دن
V
"
1 ما
با
'
ام
ن مر
"
" "البلد
17
,۱
۱۹ ا دا
.
"
داد ۹۴ ادامه
الم
ا ا
ر
. !
ا..1
;
،
،
".
ا با
-
)
:
.. ,ا
.م
اجا
1
.
"
" است . I
ها
بودجه
..
.
"
کر لیا
م
"
.
'7"..
*
| 11الة
4
''
ده
عمر
'".
:""
.
" "
ده
.
1
,
:
ہے
, , ,
"
و الله
+
-
!
.
'
'
:
/ م
. . ...
..
. م ه .
. به امانينا منها اي
ن م
F
ساله به
:
ا
ا
. ,
:
*
'
;
واري
.
او هم م
"
. بديل
م = .
و عيالها
T
حجه خخهه
*
*
1
-
.
.
*
-
.
.
*
*
+
11.1
از را
-
اور (Sili
"
.ده را
.
+
.
ار
.
لا -
دان
ام بها را سم .
۳
+
.1 |
" ." ا
*
الد
"
،
"
*
.
.
}
وه
.
:
.
ا
ل
.. .
.
'
.
|
-
}..

""
ان
*
**
البيان
.
.
*ا
*
:
ا
ا
IF
"
او ہو ا ا
!از
همه اه
و
"
اما .
.
.
اور'
خرجت
:
:"",
"
.
:
:
"
..
:
و ...
ا
:'
'
:
ا ما
او را
با
ا
".
:
،
مه
"
ت
ه
م
د
f
":"
.:
:
:::...
ا
*
1
.
:
**
ا
ا
وا
ا
ا
:را
ا
ا
ا
:
::
جنيه
1
م
-
.
.
.
***
..
:
:
.
.
.
ا
ا
ا 1- در اط
با ما
ه ما
م
.
'
'
*.
ه
الا
.
1
ادا
-
"
وت
.
.
لا
1
:
=
55
4
، .
م ه .
يم
. =.. - م
. ..
ده ،
او =
"
=
و
*
هم
لي ::
::
۰۱
من ...
،۰۱:. .
ا
ا
: ..,
. ,
اد
:
.. :
ه
.
1
**,
.
دي
ليا
.
*
.
دو
| ...
هيها بد منهم :- : -
. . ... . ده . 4
مهر، 1
...
ا
... د
ا م
و هم
ه
الا
رونا
ا
'واء
..:
: *
:.:.
:...
44
لن
.
:
و
." "
*
. .
: اهه
م
!
!
..
:
1
.
يتر
ما
:
ور
'
:
ا
|
لباس
باليد
را
بسیار
ر
ا
:
1
دسته های
را
و
فا .
... .
.
.
..وا
اه اه .
*
"
ال...
"*
"
.
پر
النور
:
"
:: بودن
.
.ا" -
ان جیسا
:
ج
*
*
م
:
ی
د
ہوگا
.
4
1
مناسب
- هالة.
لا -
...
م
1
..
ا
ی
س
م
بی
به
::
.
ا
" "
.
و
.."""""
.
L
.
.
I
.
م
من و
.
4
.
بينهم
الم
-"
۰۰.
رومان و
دیدنی
*
و
.
: IPT
"
خ دمات
4
بال
با #
'
' ' ' ' .
*
ان
:
م
الار
۱
أ
.
-:
ا ::!''
["
.
1
لا
،..
لا
... :
لا
|
را
جنين ال
"
"
اور "ی بیو_
:
$ ::
"
•
بتونه و
ت فر
ق
ة
. ټول.۲۰۰۰۰ م
مدل مو مرد
-
ا
م .......
:
"
"
.
.
4
.
. .
با
ق ده
د
اللد ۱ لیا ۴ ه
!.
.
.
بر
..."
"
::
::
TF
لم
-
|-
|
|
د. به
:
د ۱۰. ؟
.
.
-
،ارد
.
*
*
"
هلې
:
,
:
*
ا
.
1
''
ب
.
4
م ا
ا
:
لا دینا
4 ..
...
.. '
السهلا
همه ما در
اب
لایر
•
اد
في
K
:
.
.
. و بهتر
م یدم ... مجھے یہ نشا - مهند ۱۰
*
*
*
,
...
.
.
.
و
.
و
و
او و
دهها میبنا، 04، ليط
:: .
..
..
+
:
.
د
.
ه
*
"
.
-
:
"
۰
. -
.
.
| L
او رانا "
."
امر
,
.
د.م
... اما ما
به
- ج
ا
هو *
*
1
1
1
:1
د
:: :
لو
:
1
:
د
:
|
الماء و
:
و
.
۹ .. .
.
.
11
-
1-
.
از .
.
.
-
۴. -
.
-
.
!
.
::
"
وما
ا
*
ر ا
::
'م
!
.
"
. . .
. .
"
=
"
-
.
.
ج
مرغ
..
!
..
: ..
.
.
۴
هال
ز
ا
دين أشا:
ت
و
:
n
" ،
".
:
.
1
1
1
"
"-
.
1
.1
ا
... و
"
1 تا
5
دن
ته
و
:
. :
*****
|.
الب
**
.:
::.:
.
'
'',
1,
.
اور
ف
10
1
"
له "
F
: "
..ية :
.
.هم
"
و من
'' ن ن ا :" د . 1
به خون :5 ::
م . ن : . ..
.
.
:
"" ""
.ا"
"
:اج.
؟
نانو
"
..
دوا
۹۱ اهمل الصان
دین
رات
3- .
.
}
-
ای
-
:
.
- م
E
*
"
.
: ا
*
:
ن]
بر ایرانوند
و
را
ا
*
ة
"
.
. .
.
عم مذہ
نیمه بهمن
.
.
"
هم
.
.
.
.
+
ام ۲۰
ا
"
.
\
1
ة
و
-
.
.
م
.
هو
. و و
و
و
.
.
1
"
ن... ...
..
: .. ..
.
.... -
به
- -- --
"
اند.
"
پر
م
بسته
، با
از 1
f'
۱
,F I
1 .
-
م .
.
الد :
'
:
اور
ا له
.. و
ب
ا
رام
و
...
:.
1
.
به
== = ا
ا
|
.
اما
I
' '
: .. و حههمر
.
'
'
هم
" هند -
- د ند. .۱
.
*
هستند. بیٹی ام
می
م
فيلم
* نسنین
"
-مد:.
د
و
ا ا
ام .
ب
ا
ا
م
ا
اعلا
ن
'' ...
.
ا
.
ا
ا
.
هو
ا
با
من الله
"
ا
اله
-
ممد
ع باد ...
ع دد
ورود به ، و به
:
.
:
..
* *
.
, .
"
*
,
..
1:11
+
.
.
ن
=
**
..
1 =
۹۱
: . . در
وم
4
'
ما
'
:::
"
:
.
,
لا
,
, , ,
'
,
.
مها: ۱
۰
ی ملا
ا ا ا ا
ایرانی "
! تازه . .
سلامت
: ان دا ""
إنهم **
"
دلم
مداد س مت ها
م برنامه
... ,
' ان
خیابان
۱۷
عدنان اليو
را
مهاباد
ها و ماهی
.
1
أما
-
ل
. .
.
. .
.
او با ... ؟ وهله I'
::
*
**
.
''
"
.
E ما
ما
برام الهلال بابت
"
ا
'
'
'
'
'
'
' ' '
'
'
.'
' .'
|_ '' :
. .
. .
ا
ا . "
الاسنان و
ر
.
او
1
الم
ا
::
وا
د
:
و
.
"
.
*
*
الان |
۴
ما
و
::
سی
'
'.
\
*
.
م
.
ومنها
م
!
.
1
-
ا
ہے
:
4-
*
:
اه
:
.
-
.
"
نور
=
.
و ..)
:
.
،
.
د
*
همراه
"
"
.
.
به
ا
.
باران
حمل
.
1
لط
سه
: وطن
"
1
F
*
|
*
.
'|
اااه ..
وه .. . .
:::
:
:
FA, ,
مجد
.
.. ..
:
و
: " ما
:
'
.
بهمن
ماه : * * *
,
۴.
جنش
و
. . -
.
.
. . . .
..
ع
" م
.
م
و هم به ه مه .
هی
هم
دم
-
دلامونه
کده مه
رو به یه
7
,:؟
احمد
.
هو
F
:
ه 4
.
.1
4
2
-
:
''
لند +
انا : الله
:
و
"
و
"
علم
کا
1
,
1
.
،
.. .. بهمگا وات
'
ما
.1
. در ماه
سر برده
..
به
اپ
و ۱۰ انه
: 1
و با مزه
1II
"
:
ا
:
عليها
-
::
!
.
.
""
.
.
"
-
""
طر...
"
"
م
.
میر
و
.ها و== -
ا
!
+
.
.
r
-
ه
ت اج
عمان- نانو
اهور *
.3
/
:
معمر
هم
.
ب ود
.
و *
....
" .
... -
أ
مما
"... "ل
+
۱۰
گ
ا
۔
-
"
""
:
:
:
استاد امان
:
غدد
" التي
ا
أ
|
|
|
''ز
ا .
ع
ا
ا
ا ا
ا ا
ا
ا
ا "
"
"
"
. . .
"
"
الف. با. 18
1
.
وم
:
''
. م
وا
انی
"
:
:
يا
و
لا
رها 11* ۱ ، ۱
1
"
ر
.
"
.
.
.
اله
بالا
.
ا
,
1
,
م
!
علی.. ..... د
- ورود
۴۴
ماز
ا
۱۰۰
" "
"
ت
هما
1
با
:
1
"
"
.
. ولا..
*
"
یه
*
ه
است
'امنا
ا
.
:
ه
ا
" الان
واتا
ا
'
اه
""
"
ار
ار
در
فيلو
اور میرا
وا
این خود و با
دقت
و ظالم سما
...
اما بعد: ۲۰۰
، و
:
امدید !و
/
مل
ومما "
وااار و
و مهمه
..
بال
و
را
"
دیا
'
'
|
.
.
.
4
د.
و
دام
:
مه
مر
.
1
1
امام رهام.۱۰
۰۰ مه ک
ا
ا
ا
ا
,
ا
ه
1
.
|
|
دار
و
... را به
*
.
هیات
بات
۱
:الم
,اج
ا
ل
ا
.
4.
ء
"
لو
ن اسرا
، داوا" '' را
.1
دولا ن
ه : " با "
با امام ماند
ا ، ا
:
را
از ۱۴
دیدنی
ا یران
.
فهد
مر
ا
ر
دی
.
.
و
-
ني
هام وخ- --
,
,
و
.
،
اور
'
'
.
م
.
.
.
.
شر
وه
و ا هلا
/
ا
۱
ا
ا "
:
.
.
.
. .
برادو
.
.
. .. .. .. ..
(

.
2
ا
ا ا
لیس
-
--
.
.
"
و
.11
--
: .
-
و
.
.
.
*
-
.
. .
-
ب
-
ب
ن
ر ا
ر
"
"
" ا
"
"
ا
"
- " و
ا
ا
،
.
ا
"
.
.
.
:۰۰ ب
. .
. :
.
"
.
.
.
..
.
.
"
ا
ا
ا
ل
لا نوجوان
ط
"" "
:
و
مر
گر
"
:
.
11
.
ا
ر -
اہد، ا=:=:=
د
الزي FF"
... "
*
..؟ اتر "
ا اد : ده
8
و بار ، علما ن -نها
.
د
و
ا
.
"
"
:
،،، اس
،
س
,
.
,وء ولا
. .:
اعمال
ساعة
و 11
م
:
همه
.
: اب 4
..
'
3
.
خ
دا
: - ده
در
ه
-
-
د "
:
- -
-
- -
.
د ..
.د. -.
پیمب :.
'
:
دو T
=
'
:
1
اتناش
:
-
-
-
*
*
لا اله
و
ته
.
د عم مج خيخ
مه
-
.
- .
.
-
.
- -
. -
.
.
و
... . - ا ،
:
.
:
.
.
T
ها
.
.
. دوه
"
وہ
:
نا
.اه
م
۱۰۰۰
۴.
..
.
.
۲
,
۰۰۰
: ۱۶
.
د
ای به
3
:" و"؟"
.
م
"
:
"
و
5
.
P
|
و
|
. "
.
" "
.
-
.
.
"
. بي
.دند و
... ..
،
,
:
' :
اف
فر
..
ا.
..
" ::
::
".
. " "
ا
::
1
::" |
و
، الا
(
.
امی
م
م
تحلل..
".
وب
. .
.
مد - ..
"
,+4
.
+ + 1
خطتهم
ت لام،
.
ب
|
ه .
..
با
......
بار
'' اور .."
. !
:على
ام
ا
2.
.
'', "
لو
"
في . .
و
. .
:
د
:
|
.
*
.
'
,
.
اند .
ر
..
.
,
"
"
- مه
و .
.
.
.
..
.۔
*
.
. .
ه
.
7
. د
د
الزينة "الا..
ا
پ در: ۴
ل
ه ا
يرد ...
..لا
.. را
..
د
..
ا
رد
.
۱۱
ماما
تمام شده
ا
و
باران
به نام من
می بازی
.
ها 5 "
ان ما
... "
اما خ ان
"
".
"
! .
- له
"ن ها
.
.
.
.
..
ها
.
د ملا
|
لیا
و
ان
.
ترین
.
.
-.
- T F با
الا
.
.
.
. . دین
هم د مجاه
" (
امممممممممهممممم
:
1
1
: ونے
.
د
.
أ . د علم د. عبر عهده
:این :. به
.
م
ن
ربه
"
"
میان
=
=
:
" .. "م
if
و
..
.: *
: ول
.....
....
..
.
.
از :
به
به سی
'
.
.
,
*
...
"
,
م
ا
,
,
و
"
ادو
»
|
و مال
لاء
-
{
"T
-۱۹
.. زر
"
-
و
|
دوم ا
.
.
بالبالون
|
،
!
.
.
'
.
.
.
. .
.
؟'
.
...
.
.
!
!
:
۰۱ ویر :: دبی
5
:د
, وهو
-
ولا
.
ع
. ا ا
عر
لانے
. *
..
-
*
*
*
: ... . .ل
... '
عده
ای ...
.
:.
ام I
. ،، ۱۰
د
. . . .
و
.
.
.
.
.
س
.
'
'
.
حمية بمصدومه
*
"
.
"
الله مجید میبینید
. .
وفق"
-
و
ما هي
..
اسدا.
:
..
:
"
۰۰:۰۰
* * * TE
لما
اليد .
مجلة
. .
برای
.
.
و
مطار المطعم
و مد*
. ''
و
=
. .
1 .
-
4
-
.م
.. .
.
!
...
و
|
||
|
.. .
نن
.
- : لا
دا |
.
. ۱۲
كل
ا=""
بدلے
.
م.،
ة
رو
.
و
" !
E
...
: : : :
ارا
.
|
: :
:
ایمان
:
":
:.
:
-
.
|
-
ها
..
:
و ۲۰۶ - ہم سپرده
:
:
'اء *
: '
'
*
.
.
ما
۔
. .
.
به همهمه این
همه باید به مصر خمسه
.
:
1
.
" : .
*
معده
":
اولا
ا
ا
. . ...
!
و بخرم
.
*
+
"
.
1"
*
.
.
.
-
و
+
و
.
":
.
لملامین ، که ۱۰ به
.
ا
:اول ,
بدء
، ،
'':
.
م.
...
وما
کی
.
......
ان
. . . .
.
دن
ا
و
ر
۱۰
و من
ء
ا
:
.
.
مم
من
.
.-
ہو. 4
:
* *
*
با
:
:
الراي
الدوامة
ردم با
ER
:
او
۲۲ !
را که ..! 1
را
{ t
،
+ دولار
-A
]
1"
",
.
ن
.
','
تا حالا
.
** وم
و
.. + +
مه
.
.
:
:
أن
ان)
باء -
کو
با جواب
..
همه
ا
هما
"
" :
_
...
.
::
..
ا
ا ا
:
1
. '
.
و ۲۰ هواء
و
:
.
:
+
,
:
:
"
..
'
:
و
"
1
:
ا
م
جملایا
و
؟
ه
:
1
*
.
:
ادار
*
ب
"-بند
والا
ا
.
.
."
ور ::.:. -
:
:
انه من
......
و الا
به
::
.1
ا
ا
.
.
ا
عا . ا :1 1 به
"
t
ده
ها ولاد ..
" -
ان
.
محمد،
"
1 -
1
شاهد ... امام
.
.
.
!
.۱
. !
... ... ... . . .
.
واژه
و . . . . .
دندان
,
.
=
ام
تر
0
دارد (1)
"الننناير
-
- !
جدا,, 'اب
در " ."
ز
درمان امام
و باطن 51 "
'
د ناد
تجاری
'
و:
"
"
I.
.
.. .
'
1
س ال ۹۷
تا ۱۹۹۰
جاتا او با ایران را ادا
-
مالی
,1"==
1
|
باد
در
ال
له
..
'
به
-
.
"
.
.
ا
، ا
ء
"
1
*
...
- مد
ا
*
زاد :...
لا ،
}
ين
:
+
.
-
امام
:
1
ء
دیا'
. .
اره
. .
...
... .
..
:
با
*
بن
و
..... م
-
بندر
:
د
و
'
4
.
n
=
ا
*4 و ومي، و
اور
حس جما
.
خانواده
: ما
*
م
ء
این
.
ه
*
م
|
. F
|
ی
م
-
:
-
- له
:۱
ده .... م :
له خه که
"
"
.
:
داد ماه :
مسجد
مه
: وطن
C
رد
من
" بمطعم
"
ژ
.
.
.. .ه -
1
.
4
في
-
-
-
-
.- .
۱۰۰ :
لا ..
.. ..
.. .
-
هم
"
ي
سيرا . 14 سنه
=
=
FIF
*
همه جانبه به
ما
ص فوی
|
. وء
.
ی
--
.
=
1 -
..
.
عمله
+
++
++
اسم مع مواصم
+
انعم الله عنهما
ان
بار
* 4.
.
تب :
اه.
الغد".. ...
"
، ،
. .
"
.
.
.
.
'ر : ۹۰ دلاليه
.
.
آل *
.
.
:
....
الم .
::.
ا
ا
و
"
"
.
.
ي
.
اسما ء :
ا
...
ܕܕܪܐܪ ܕ
.
.
'' .
1
داع
ء
".
" "-
I'
. شد
، شان
-
و
،
.
۲
.
. .
-
-
را
-
.
.
و
" ::
.
:
:
۱۰۰
'
.
"
"
.
و
"
له
l
سار
,
:i
"
:.
:
'
ا نا
ء
.
ا
ا-
ر
۰۴:L:
:
"
ا
ا
.
.
لا
. آن
اج
-
ا
د ارا ان را
رو
ا
ا ا
ا م ا
:- اجلاس
"""
"""""""""""""
1
.
:
ا لرابط
اي انا
و
مهار *
ور عالم
|
.
.
*
. ا.
ا "
.
.
.
.
. . .
ما
'
امام
ل ..
ز مر
و مهنده منافسه مما
الح
. .
*
.
.
.
.
.
it ::
اعت
.
ا
:
.
| کو
,
.
ا
|
|
.
ها
|
|
رها
انا :i
والد
... نه
:
"
. "
محمد
و م ا ا
رها
ا ا
.
یه و
ه
..
''
ملا:
"
"
" "
"
"
!او
"
... "
ا
م . .
,
موخ و
1
ته
4
'
.
الوا
....
:
ار
ا
ما
*
:
حجم و
-
اور
""
'\.\
بد نیز به
رام
حد
}
*
t;
..
..
ORNL--LR-DWG 75068R3
100
300
SURFACE TEMPERATURE (°C)
500 700
900
(x102011
PROBABLY STABLE
PROBABLY UNSTABLE
• BMI-32
• ORNL-46
À BMI-33
8 BMI-GCRE
G KAPL
X NDA-1
PWAC
I ORNL-21
FISSION DENSITY (fissions/cc)
NUMBER OF
SAMPLES
*(8)
ORNL (1963)
ORNL (1958)
BM! (1961)
---
(12)
_
OPEN SYMBOLS INDICATE
FAILURE
F!LLED SYMBOLS
INDICATE NON-FAILURE
(8)
(8)*
18
(2)x
(2)x.
!
(2)
I
(2)*
OO

200
400
600
1800
2000 2200 2400
800 1000 1200 1400 1600
SURFACE TEMPERATURE (°F)
Irradiation Stability of UO 2 - Stainless Steel Dispersions.
=
.
...
..
.
.
.
.
.
.
.
se. --:- -
.
.
.
.
.
. .
at
-
-
3/ 17 / 167
DATE FILMED
.
511
END
.
.
WA
YLE
11
446