ML19323G338
| ML19323G338 | |
| Person / Time | |
|---|---|
| Issue date: | 05/09/1980 |
| From: | Rachel Johnson Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19323G339 | List: |
| References | |
| REF-GTECI-A-11, REF-GTECI-RV, TASK-A-11, TASK-OR NUDOCS 8006020198 | |
| Download: ML19323G338 (50) | |
Text
_ _ _______ _ --___-_______-_________
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UNITED STATES
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t NUCLEAR REGULATORY COMYtsslON
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..% v,[ }c WASHINGTON, D. C. 20555
($
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MAY 91980 Generic Task No. A-ll MEf10RANDUM FOR: Distribution RR0ft:
R. E. Johnson, TAP A-ll Manager Generic Issues Branch, DST
SUBJECT:
REPORT ON MEETING OF TECHNICAL TEAM, TAP A-ll The second technical meeting of the TAP A-ll tean was held at URC Head-quarters, Bethesda, Maryland, on April 9-10, 1980. is a copy of the Meeting Notice. Enclosure 2 is a copy of the Agenda. Enclosure 3 is a list of attendees.
At the meeting, each attendee was given a copy of Task A-ll, Revision 3,
" Reactor Vessel Materials Toughness," April,1980. Additional copies are available by request to the TAP Manager (Johnson).
During the meeting, the issue of problems on tasks which could occupy the attention of the team came up repeatedly. Several " shopping lists" had been prepared at different times by several people prior to the meeting. Copies were handed out. The lists have been recopied and are included here as Enclosure 4 (of 6 pages). By this letter, comments are solicited from all team members by the TAP Manager.
Prof. Paris reviewed his analytical results. Enclosure 5 is a scaled-down copy of his easel chart. Enclosure 6 (10 pages) is a set of his viewgraph charts.
Paris concluded that the final equations for the leak-before-burst analysis were independent of the assumptions made with regard to the plasticity nodel (i.e., it was the same for plasticity-modified LEFM, power law hardening, Ramberg-Osgood, etc.). The basic approach was to develop the ratio J/T for the structure being analyzed * (where J = applied J-integral; T = applied tearing modulus), in which case the stress cor-rection cancels out and the shell correction function becomes analytic.
For essentially zero crack growth, J/T is a straight line with slope
- Specifically: a cylindrical shell (the r.p.v. beltline) with a through-wall crack.
E THIS DOCUMENT CONTAINS POOR QUAUTY PAGES 8006020198
e (for a typical vessel) of about 500:1. Using available materials test data, curves of J (material) as a function of T (material) formed a family of curves (roughly: hyperbalae), ranked in proportion to the corresponding Charpy upper shelf energy (the lower the USE the closer the curve to the origin). Unstable growth would be predicted at the intersection of the applied and naterials J-T curves. The approach led to the tentative conclusion that leak-before-burst would be likely for Charpy USE of 50 ft-lb and above.
Dr. Merkle presented a summary of his analyses. Copies of his view-graphs are attached as Enclosure 7 (10 pages).
Merkle's analysis essentially supported Paris'. He showed that the concept of using the J-T relationship to establish instability could be tangent modulus) relationship with instability identified by tbe(stress-related to the Euler buckling analysis, which utilizes a o - E inter-section of the beam and materials curves.
Dr. Riccardella took the tearing modulus analysis and applied it to an hypothetical vessel of typical dimensions and properties for the HSST Intermediate Test Vessels, starting with a surface crack and allowing growth to a through-wall crack with a length about equal to the starting part-through crack surface length. His result showed that the observed vessel behavior (i.e., burst, rather than leak-before-burst) would have been predicted. Therefore, the through-crack analysis showed no in-consistancy.
There was a discussion centered on the term " upper shelf" and the various means of establishing it. Prof. Irwin dist.ussed facture test results in which the spring constant was varied. He said they showed that one must oo SOF* (maybe as much as 100F') above the onset of the CVN upper shelf to totally avoid cleavage instability af ter some initial tearing.
Dr. Loss presented experimental data and analyses; copies of his view-graphs are included as Enclosure 8 (14 pages).
Using single specimen unloading compliance methods, his J-R curves showed continously decreasing T with J, unless cleavage interceeded.
Graphs of J = f(T) showed a family of hyperbolae, decreasing rather regularly with C U.S.E.
Taking J at T = 20, the data correlated with y
C enerny and with absorbed energy per unit flow stress 'ut with c
ygreater scatter. Taking J along the line of slope J/T = 50 lb./in.
improved both correlations (a toss-up as to which was better). As Paris had pointed out and Riccardella confirmed, the ratio J/T for a vessel with a through-wall crack would be about 500 lb/in. so the significance at a value of T of 50 lb./in. was that it picked off values of Jmati associated with the leak-before-break roughly _1/10 of the Tappj criterion.
l l
I
e
,. Discussion during the two-day meeting was too extensive to be documented in any detail. A few things which made an impression on me are listed as follows.
1.
Paris noted the importance of making aa corrections to the J-R curves before trying-to use elastic-plastic fracture mechanics (e-p f.m.) in a search for correlations with Charpy data or as input to the vessel analyses.
2.
Cooper suggested that for PWR accident analysis, the upper limit for pressure could be the " set pressure" (giving a stress of about 26 ksi) or the " accumulated pressure" (giving about 30 ksi).
3.
Some questions the Team felt should be considered were:
a.
What is the likelihood of cleavage fracture intervening after some tearing?
b.
What is a sufficient amount of e-p f.m. data?
c.
can data from specimens under bending loading be applied to j
tensile instabilities in hardware?
d.
What is the role of crack arrest in the elastic-plastic pressure vessel problem?
4.
I was asked to determine the availability of WCAP Reports on the pressure vessels at the Turkey Point and Point Beach plants. They are marked nonproprietary but not to be distributed outside of Westinghouse or its licensees without the customer's approval.
Since the Team is enjoined by NRC restrictions, I believe they could review the reports as if they were NRC Staff members. Anyone who wants to pursue the matter can contact me.
i 5.
Suggested topics which the materials engineers should consider were listed, as follows:
a)
Evaluate the tendency for J = f(aa) data to follow a power law (straight-line curve on logarithmic coordinates);
b)
Compare multiple (aa by heat tinting) and single (unloading 1
comoliance) specimen J-R curves to see if the unloading influences the shape (curved or straight);
c)
Include aa adjustments in J-R curves.
d)
Evaluate geometrical factors (e.g., size effect and side groove effect) on J-R curve power law;
. e)
Correlate J-R curves with tensile parameters, if possible; f)
Correlate J-R curves with Charpy data (e.g., C U.S.E), if y
possible. Include C lateral expansion data in this effort.
y 6.
It was agreed that an action plan was needed for the analytical effort. Some considerations were:
a)
Apply the e-p f.m. analyses as now developed to the Ft.
Calhoun RPV (Paris has data on vessel);
b)
Utilize RPV data available in computerized storage and retrieval program, MATSURV (Strosnider, NRC, is preparing a NUREG report on the program);
c)
NUTECH can bring some manpower into the calculation effort; d)
The e-p f.m. analyses should be applied to the HSST ITV results.
7.
Irwin promised to prepare a written contribution to the A-ll NUREG covering the background leading to the leak-before-burst concepts.
8.
Cooper agreed to draft a section of the A-11 NUREG dealing with safety margins and code requirements.
There are two other things, outside of the specific subjects of the meeting, which I would like to call to the attention of the Review Team.
The first is a paper by Mike Aycock, NRC, presented at the ANS Conference in Knoxville in late April, titled: " Unresolved Safety Issues - Where Do We Go From Here?". With minor modifications by me, the definition given for an unresolved safety issue was:
An Unresolved Safety Issues is a matter:
(1) affecting a number of nuclear plants; (2) that poses important questions concerning the adequacy of existing safety requirements; (3) for which a final resolution has not yet been developed; and (4) that involves conditions not likely to be acceptable over the lifetime of the plants it affects.
I
. f Since that is what the Review Team is working on, the definition should clarify and guide the1r activities. From the same source, the steps to resolve an issue were given as a table:
TABLE II.
STEPS IN RESOLVING AN ISSUE STEP PRODUCTS 1.
Identify, Investigate & Evaluate Decisions regarding:
Significance of Potential Issue
. Is/Is Not a USI
. Priority
. Need for Interim Measures 2.
Plan Technical Approach, Resources, Task Action Plan Schedule Aqua Book 3.
Generate and Assemble Necessary Technical Reports Technical Information 4.
Evaluate and Decide What Licensing NUREG Report Containing Requirements are Needed for Public Proposed Requirements and Safety Safety Evaluations 5.
Peer, Public, ACRS and Industry Comments Review 6.
Promulgate Requirements Orders, Letters, Rules, Guides, Standard Review Plans 7.
Implementation Changes in Design, Testing Operation, Maintenance, Training, etc.
Obviously, the Review Team is working on item 3.
Steps 1, 2, 4 and 6 are performed by the NRC staff and management. Use the above to both guide and limit your efforts.
The second is a dialogue between Marston (EPRI) and Randall (NRC) dealing with some of the RPV problems. Two letters are enclosed (Enclosure 9)
. with tne authors' permission. Please excuse a few editorial marks made by me. Hopefully, the letters will stimulate further discussion among Review Team members.
M f0W m
y Richard E. Johnson TAP A-ll :anager Generic Issues Branch Divsion of Safety Technology
Enclosures:
As stated l
^.e DISTRIBUTION MAY 91960 Central Files Generic Issues Branch R/F S. Hanauer M. Aycock R. Mattson K. Kniel F. Schroeder D. Eisenhut V. Noonan L. Shao J. Strosnider R. E. Johnson P. Kapo R. Gamble R. Klecker W. Hazelton J. Knight P. Check S. Pawlicki W. Regan P. Randall, OSD C. Serpan, RES M. Vagins, R NRC PDR ACRS (5)
Accessions Unit Mr. R. G. Berggren, CRNL Dr. D. A. Canonico, ORNL Dr. W. E. Cooper, Teledyne Eng. Services Prof. H. T. Corten, U. of Ill.
Mr. J. R. Hawthorne. US Navel Research Lab.
Prof. G. R. _Invin, U. of Maryland F. J. Loss, US Naval Research Lab.
J. G. Merkle, ORNL Prof. P. C. Paris, !4ashington U.
Dr. P. C. Riccardella, NUTECH Mr. G. M. Slaughter, ORNL Dr. Theodore U. Marston, EPRI Dr.'M. F. Kanninen, BCL Mr. John P. Gudas, DTNS R&D_ Center I
7-'s n:. "-
ENCLOSURE 1 UNITED sit.TEs e'
f E... T' i
"'L' CLEAR REGULATORY COMMISSION
, %C z e e
wasmNCTON. D. C. 20555
% %.:...y' l GR e a %
Generic Task l o. A-ll
- '.D']PA1;DUM FOR: Vincent S. Noonan, Chief, Engineering Branch Division of Operating Reactors FROM:
Richard E. Johnson, TAP A-ll Manager, Engineering Branch j
Division of Operating Reactors S'JS]ECT:
MEETING NOTICE: REVIEW OF PROGRESS ON TAP A-11 CATES / TIMES:
April 9,1980 - 10:00 a:n April 10, 1980 - 9:00 am LOCATION:
Roon F-110 Phillips Building i
? ;F.00S E :
OR:;L o :reser.t progress items and establish action plan 'or the immediate future. Specific presentations will ir.ciude elastic-plastic r.).v. analysis (Paris and Merkle) and e-p fracture toughness results/ correlations (Loss, Eerggren and Canonico).
PA? ICIPANTS:
NRC, ORNL, Nashington U., NRL, ORNL Sub-Contractors and visitors.
) hMs W
.b Richard E'. Johnson, TAP A-11 Manager Engineering Branch Division of Operating Reactors c::
R. Gamble R.. Klecker i
l!. Hazelton J. Strosnider P. Randall R. Johnson S. Hanauer
'. Aycock C. Serpan M. Vacins "r. R! G. Berggren, Oak Ridge Nat. Lab.
n. D. A. Canonico, Oak Ridge Nat. Lab.
r 4 -
Dr. W. E. Cooper, Teledyne Engr. Services Prof. H. T. Corte, Dept. of Theoretical and Applied flechanics i
l'r. J. R. Hawtho rte,.*;RL
~
3rof. G. R. Irwin, ' Cept. of Mechanical Engr.
- r. F. J. Loss, "RL Dr. J. 5. :*erkle, Ca< Ridge.';at. Lab.
Prof. P. C. Paris,. ashington U.
- r. P. C. Riccar:si a 'f;UTECH "r. G. ;' Slau; :e, dak Ridge '.3t. Lab.
I
{./
/
rpbgg 4LO o
(
L a
e ENCLOSURE 2 (Meeting Notice is Being Distributed by NRC)
AGENDA SECOND TECHNICAL PLANNING SESSICN CN TAP A-11:
REACTOR PRESSURE VESSEL TOUGH:.'ESS Wednesday and Thursday, April 9-10, 1980 April 9, 1980 10:00 AM Introducticn G. M. Slaughter (ORNL) l Review of Pertinent Points R. E. Johnson (NRC) from February 27 Meeting Elastic-Plactic Analyses Applicable P. C. Paris (Wash. U.)
to Reactor Pressure Vessels J. G. Merkle (ORNL)
Elastic-Plastic Fracture Toughness F. J. Lcrs (NRL)
Results/ Correlations R. G. Berggren (ORNL)
D. A. Canonico (ORNL)
Other Ccnsideratiens All Participants (a) Ccmparissa cf Tearing Instability Method with other Methods (b) Data Ccmpilation (c) Safety Margin (d) Other Planning and Assignments All Participants Summary R. E. Jchnson G. M. Slaugnter April 10, 1980 7
'4 Adjournment
4 ENCLOSURE 3 ATTENDEES - A-ll fleetino, April 9,1980 Name Organization Phone Richard E. Johnson NRC/ DOR /EB 301 492-7385 Jack Strosnider NRC/ DOR /EB 301 492-7356 Paul C. Paris Washington U.
312 726-2942 Karl Kniel NRC/ DSS 301 492-7139 Peter C. Riccardella NUTECH 408.629-9800 Herbert T. Corten Univ. of Ill.
217 333-3175 William E. Cooper Teledyne Engrs. Services 617 890-3350 Frank Loss NRL-202 767-2562 Russell Hawthorne NRL 202 767-2617 George R. Irwin Univ. of fiaryland 301 474-4755 Milton Vagins NRC/RES/'t&MRB 301 427-4262 Charles Z. Serpan, Jr.
NRC/RES 301 427-4262 Pryor N. Randall NRC/OSD 301 443-5997 Dominic Canonico ORNL/M&C 615 574-4465 Gerry Slaughter ORNL/M&C 615 574-4267 John Merkle ORNL/ETD 615 574-0661 Rey Berggren ORNL/f1&C 615 574-4468 l
ENCLOSURE 4 Shoppino Lists flarch 5, 1980 A-ll Tasks 1.
shell effects for a.
very large crack (e.g., through-wall, 2a long; a=R=10t) 2.
sample calculation on an actual RPV (Ft. Calhoun chosen) 3.
analyze data: see how well the Ramberg-Osgood rodel (being used in the PRV analysis) describes the experimental J-E curves for PRV steel; irradiated and nonirradiated.
4.
need to develop more J vs. T diagrams, esp. to higher J-values.
(experimenters should not stop J-R curve test at t.a = 1.5 m; can't understand why ASTM set such an arbitrary limit, anyway.)
5.
Correlate J-T curves with Charpy data.
6.
Apply analysis to a variety of RPVs (all (?) HSST ITVs).
7.
Identify holes in the data base - take steps to fill them in.
8.
Codify the e-p leak-before-break analysis.
Solicit EPRI (Ted Marston) to participate, release relevant data.
Open questions to be considered (and answered) by the A-ll Group.
I.
Clevage intercession: can it be predicted?
II. If the RPV crack runs (fast fracture) but arrests outside the beltline region (low fluence; high toughness), what are the dynamic effects (quantitatively)?
III. As diagrams and correlations are developed, do we have a statistically-significant data base?
P. C.-Paris R. E. Johnson
i 1
, Enclosure 4 i
Shopping Lists March 4, 1980 ADDITIONAL WORK TO BE DONE ON " LEAK-BEFORE-BREAK" I.
Analysis (Paris will work on these) a (a) For A =
- 1 (or Greater)
VRt' A shell correction factor should be incorporated in leak-before-break (Paris to analyze).
(b) For (See CSNI - NUREG - Vazquez-Paris & Cheissoux) "Shell Effects". Also look into possible plastic (zone) instability failure condition (Paris) (See Ditto)
(c) Do analysis on typical example nuclear vessel for L-B-B.
(Paris & Johnson to analyze).
II. Material Data (Need Trocos to work on these)
(a) Need stress-strain curves for typical basr. & weld materials to various degrees of irradiation in order to redo hardening analysis (get c, E, v, 5, n for each (& correlate on cross plots?).
(b) Need further R-curve data plotted on J vs T diaaram. Should be run to higher J values (bigger aa than T 5 mm) (but valid:
> 10, e
aa > 10%b, B > b, etc.)
(c) Study correlation of J vs T Jiagrams with respect to Charpy upper shelf core $katTon5"t (d) Redo hardening analysis for T
&J for various "x & n values found in II (a).
appl appib III Open Ouestions (Whole Group to answer?)
(a) Does cleavage intercede above transition temp? or well above transition temp? (how high?)
(b) For running crack in " belt line" which might arrest outside belt line are dynamic effects important? (betterorworse?)
(c) Do we have a " statistically significant" data base in II (a-d)?
. Enclosure 4 Shopping Lists IV. Application to Typical Reactors - Many (a) Simply take typical reactors of all kinds (sizes, material properties, beginning to end of life) and look at implications of L.B.B (NRC-ORNL Staff?)
V.
Identify any areas of lack of data or understanding and ensure programs to take care of these itemi-'(NRC).
VI Formulate " Code" type rules for L.B.B. computations and requirements (Whole Grouo).
P. Paris
, Enclosure 4 Shopping Lists Analysis to Define T vs J Relationships for app Problem 1 Upper Shelf Problem Part through flaw Nominal Stress = 50 KSI Neglect Residual Stress Neglect Thermal Stress Material is on upper shelf Problem 2 Transient Problems Part through flaw Real pressure stress Real thermal stress (for rance of transients)
Real resicual stress Material is not on upper shelf R. Gamble
. Enclosure 4 Shopping List Shopping List per Paul Paris, et. al.,
At a Meeting at the NRL, March 25, 1980 1.
P vs 5 Record 2.
o vs e Curve 3.
R-Curve 4.
J vs. T Curve 1.
Spec. No.
2.
Spec. Type and size y+
uit 3.
o =
O 2
4.
% side arcove 5.
C (USE) y 6.
Trans. Temp.
7.
Test Temp.
8.
Notes on Cleavage if present 9.
JIc (by an Std. as possible)
- 10. J vs T vs a vs aa/b; for at least 5 points from J to as close to C correlation line as Ic y
possible.
Correlation a
C vs J(T=20) y b
J(T=10) c J/T = 50 Normalize with a ?
o-Notes:
1.
Is J corrected for a) crack extension
. Enclosure 4 Shopping List b) formula c) side grooves d) etc.
2.
Is La corrected for a) specimen rotation b) Heat tint or what?
3.
List Estimate of accuracy on a)
J, dJ/da, ca
o EfiCLOSURE 5 h
\\
,a
,:k < D
% /
[
gpA g
=
au-go.
d6 b
pg_
- e Tr <.
7
/%A l
l A ct.
I O#
Y E QV3L detAr = 7 APPL.
WL d{
d ges, or w.
@ &AOLE
~['fgp> T ppq 4
S_YA BauT'r dT,
> dTi d A, yen U
l 9 0.' % 3 uN&asLG ~1~~urr = Tag
%. < Ta re t.
i G -'1 I
A Trae rr s'g e t t
% 49yL E.
[* CL Q.
Co (U2Ecrisu j San s Ern es s THat G n n n-cc TIT
'~
Tk2XY Y
=
c n n o cmu r-(t I
a E
l + 2 '^ Y/Y Y_.
=
&G
~)~
lb fYl-
) (D O O l
[& > 6o v.c.,
a, t-3
ENCLOSURE 6 y'
oemt-owG N555 ETD J-BASED " LEAK BEFORE BREAK" ANALYSIS I
h.
t J
J 1
C,= 70 y
y t
h e
50 l
i la (20 Tu t
i JMAT (T = 20' X
X X
1 C, REQUIRED C - UPPER SHELF
{
(REQUIREDI 2,4 l[
J4ppe =4:g 3
l!
lbl I
APPL
-: J r (NO PLASTIC INSTABILITY) a p, 0 a/E :@]
J. T
=
,1 t
f SHELL CORRECTION STRESS F ACTOR HARDENING ANALYSIS
(@l OO
,g,
"($f e_ _ /g 1
. _ __ e 0
i f
A=
u s
= Enclosure 6 ORNL-WS-8424 ETD ANALYSIS EQUATIONS 2
JAPPL
- 00 a/E { } (Y )
Y = Y (a/y/Wt)
FOR (1)
L. E. F. M.
I
{}=r(o/o)2 o
(2)
P.Z.C. - L. E.F.M.
{}=x(a/o)2 f j _ jfg (gfy 3 (a/co < 0.67) 2 o
9
/
(, 2 ( STR ESS 6 ( STRAIN j (3) STRIP YlELD
{ } =(8/r 7)ln sec (w/2 o/c )
o
( STRAIN 0.7 < 7 < 1 ( STRESS (4) POWER HARDENING l
r e/eo = E (o/o )"
o
{ } = s f * (a/c )" + 1 o
(f * = n (n = 1), 2.22 (n = 3),1.25 (n = 5),
0.88 (n = 7), ETC.)
(5) RAMBERG-OSGOOD (( STRESS) e/eo = o/oo + 5(o/o )"
o
{ } = ** (o/o )2 + G
- a* (o/c )" ^ l o
o g
(** AND G* FROM ZAHOOR)
\\
e D
0 Enclosure 6
/
FOR (Y)
- SHELL CORRECTION FOR LONGITUDINAL CRACK IN CYLINDER Y = (1 + 1.25 A )1/2 x4j 2
(0.6 + 0.9 A) 1<A<5 (A=a/8)
FOR THIS AND OTHER CONFIGURATIONS SEE ROOKE AND CARTWRIGHT HANDBOOK AND OTHER SOURCES.
FOR T
-WITH o = CONSTANT, DIFFERENTIATE J dJ/da = l}
(Y2 + 2 A Y Y')
TAPPL = E/00 FOR ALL CASES ABOVE THEN FOR J/T J/TIAPPL " 00 a/E [1/1 + 2 A (Y'/Y)}
NOTE; 1)[ ] > 1/3 PLASTIC ZONE INSTABILITY r = JE/# n o OR y
0 oh U
dJ BJ MAT 4
APPL _. T da
-$r
- APPL Br da
,b y
IF (o/oo < 0.67) THEN:
TAPPL > # n (UNSTABLE)
\\\\
OFINL-DWG 80--4561 ETD f OR T ESTIMATES OF FOR LEAK-BEFORE-BREAK OF A533B APPL E
U
.5 1.4 I
I I
l l
l l
l c@
s B
Y gob Lgf\\ g.
POWER HAFLjNING
~
C e
b, y'~~~
V
- ' V,,_,n LRAMBERG-OSGOOD 1.0 STRIP YlELD ELASTIC-POWER HARDENING FOR A5338 ~93 C 4
o N
1.115 o
60 ksi Tv
s o
08 BEST VALUES FOR 8
n
= 29 X 1@ ksi -
(PLANE STRESS) c/c * "/"O +
I"/"0 "
I 0
OG NOTE:
J=
ll oo /E a T-ll 0.4 T
I I
I I
i i
i i
ff 0
10 20 30 40 50 60 70 80 30
( T3 ppt)
O e
o Enclosure 6 ORNL-DWG 80-4500 ETD I
STRESS FACTOR FOR J AND T i
I l
l l
(FOR USE WHEN n/oo < 0.67)
N 0.6 g
9 o )2 4+
0 32 j>
,s 6
l 1
ks 1-s O.4
_o 5
0.3 0.2 NOTE:
f (SHELL COPRECTION)
J=0 a/E 0
f f (OTHER SHELL CORRECTION) f T=
a/E NL SHELL CORRECTION) _
0.1 0
l i
I 9
i O
O.5 1.0 1.5 2.0
(
ORNL-DWG 80-4554 ETD RAMBERG-GSGOOD HARDENING - STRESS FACTOR FOR J AND T e
3
$5 10 (FOR USE Wi1EN n/o 0.67) g SS d
" "U "U
08 b
p@
FOR A5338 ' 93"C i
fo 60 ksi 2
1.115 g
3 06 E - 29 X 10 ksi n 97/
e n\\
l
{
o 04
[
\\"U s
(1 _.1 [_ "_
NOTE-f (Si1 ELL CORRECTION) l 2 (ooj j J=o 7 a/E g
f (OTi1E R Si1 ELL CORRECTION) -
02 T=
J/T = o 7a/E (FINAL Si1 ELL CORRECTION) g I
I I
I I
I I
0 O
2 4
6 8
10 12 14 46 h
e Enclosure 6 ORNL-DWG 80--4568 ETD SHELL CORRECTIONS FOR LONGITUDINAL CRACKS IN CYLINDERS 5,s j
j i
1.0
\\ [1/1 + 2 A (Y' /Y)]
N N
N 4
N 0.8
=
\\
l
[\\
\\
=
()
N N
h3 N~
.O.6h 5
5 N
s o
o o
(Y2+2AY Y')
%'Y o
3 O
E "2
=
a 0.4 g 2
(Y )
I i
NOTE:
0.2 2
J=00 a/E { STRESS FACTOR} (Y )
l T=
l STRESS FACTOR} (Y2+2AY Y')
l l
J/T = 00 a/E (1/1 + 2 A (Y' /Y)]
O O
O O.2 0.4 0.6 0.8 1.0 A=a/yIii
. Enclosure 6 T
ORNL-DWG 80- 4559 ETO SHELL CORRECTIONS FOR LONGITUDINAL CRACKS IN CYLINDERS 80 i.6 i
j (FOR 1 < A < 5)
NOTE:
J=c 2a/E l STRESS F ACTOR} (Y )
2 o
T=
l STRESS FACTOR l (Y2 + 2 A Y Y' )
J.T = c a/E {1/1 + 2 A (Y'/Y)]
o 60 1.2 l
y E
5 3
o N
O 3 50 q 1.0 y 3
\\
U c
\\--
5
\\
O c
I 0.8 m w
40
\\{1/1+2A(Y'/Yli
\\
\\
(Y2 + 2 A Y Y' )
30
\\
0.6
=
\\
\\
~
\\
20
\\-
f 0.4 10 (YD 0.2 0
~
I 0
O i
2 3
4 5
l
) = a/[ Fit I
_g.
ORNL-DWG 804567 ETO
"> HELL CORRECTIONS FOR CIRCtMFERENTIAL CRACKS IN CYCLINDERS I
d 7
g j
j (FOR 1 < A < 3.5)
G 6
f
-+--
1 i
l 5
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