ML20045C740

From kanterella
Jump to navigation Jump to search
Summary of 930603 Meeting W/B&W Fuel Co,Robatel,DOE-HQ,DOE- Idaho,Er Johnson & Eg&G Idaho in Rockville,Md Re Model BR-100 Spent Fuel Shipping Cask
ML20045C740
Person / Time
Site: 07109230
Issue date: 06/16/1993
From: Withee C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 9306240279
Download: ML20045C740 (51)
v • d • e


Text

.

p,ft Mo r

UNITED STATES 8*'

NUCLEAR REGULATORY COMMISSION n

h WASHINGTON, D, C. 20555

%,"*"/

JUN 161993 IMTB:CJW 71-9230 MEMORANDUM FOR:

The File FROM:

Carl J. Withee, IMTB/IMNS/NMSS

SUBJECT:

MEETING

SUMMARY

CONCERNING MODEL NO. BR-100 PACKAGE' Attendees NRC BWFC DOE-HO E.R. Johnson Ross Chappell George Vames Bill Lake Donald Nolan Carl Withee Bill DeCooman Meraj Rahimi Marissa Bailey.

Mahendra Punatar Henry Lee Patrick Doran DOE-Idaho LG&G-Idaho I

Nancy Osgood Tom Zielinski Mel Jensen i

Bernie White Robatel i

Li Yang Jean Fran ois Lafleur i

Introduction A meeting was held at the request of Babcock and Wilcox fuel Company (BWFC) at-Rockville, Maryland, on June 3,1993, to discuss the Model No.- BR-100 spent 1'

fuel shipping cask. The meeting was held to inform the NRC:of changes in the cask design, impact limiter test results, and pin puncture and buckling analysis results.

A copy of the briefing slides is enclosed.

j Discussion Burnup credit for the criticality analysis will not be requested initially.

It was decided that a separate meeting to discuss the fuel basket-design in detail would be beneficial. The applicant was also advised to meet with the NRC on the testing plans before. performing' final quarter scale testing.. The results of'various pin puncture analyses were presented and discussed.' ~ Pin.

puncture will-be included in the~ testing program.

During'.the. discussion of-the buckling analysis, it was concluded that the properties used'for lead-need to-be confirmed as being appropriate. An application will not-be submitted

{

'until late 1994 at' the earliest.

.. N

-[

di i 9(y o-Carl J. Withee

'd Transportation Branch Division of Industrial and-Medical Nuclear Safety, NMSS -

j

Enclosure:

Briefing Slides h

,h gggw 00

$00 b

$0

IMTB:CJW Distribution:

NRC PDR 71-9230 w/o encl:NRC FC NMSS r/f Attendees Meeting Notebook MEMORANDUM FOR:

The File IMTB r/f CEMacDonald FROM:

Carl J. Withee, IMTB/IMNS/NMSS

SUBJECT:

MEETING

SUMMARY

CONCERNING MODEL NO. BR-100 PACKAGE Mtendees NRC EL4FC DOE-HQ E.R. Johnson R'

Ross Chappell George Vames Bill Lake Donald Nolan Carl Withee Bill DeCooman Meraj.Rahimi Marissa Bailey Mahendra Punatar Henry Lee Patrick Doran DOE-Idaho EG&G-Idaho Nancy Osgood Tom Zielinski Mel Jensen Bernie White Robatel E

Li Yang Jean Fran ois Lafleur Introduction A meeting was held at the request of Babcock and Wilcox Fuel Company (BWFC) at Rockville, Maryland, on June 3, 1993, to discuss the Model No. BR-100 spent a

fuel shipping cask.

The meeting was held to inform the NRC of changes in the cask design, impact limiter test results, and pin puncture and buckling analysis results. A copy of the briefing slides is enclosed.

Di sct. uion Burnup credit for the criticality analysis will not be requested initially.

It was decided that a separate meeting to discuss the fuel basket design in detail would be beneficial. The applicant was also advised to meet with the NRC on the testing plans before performing final quarter scale testing. The results of various pin puncture analyses were presented and discussed.

Pin puncture will be included in the testing program.

During the discussion of the buckling analysis, it was concluded that the properties used for lead need to be confirmed as being appropriate. An application will not be submitted until late 1994 at the earliest.

Carl J. Withee Transportation Branch Division of Industrial and Medical Nuclear Safety, NMSS

Enclosure:

Briefing Slides b

0FC IMTB IMTB CJWitheehN' RChappell NAME DATE 6/s/93 6/ /93 I

C = Cover E = Cover & Enclosure N = No Copy l

OFFICIAL RECORD COPY

/

..__r.

'[il?Q 1

BR-100 INFORMATION MEETING.

' o ld0 ROCKVILLE, MARYLAND

)

y JUNE 3,1993

'i

y.[ : (

l

-g

.a 9:00 a.m.

Introduction and Project Status DOE-HQ.

9:15 a.m.

New Cask System Design Features.

' BWFC :

?

~

~

a 9:30 a.m.

1/4 Scale Impact Limiter Acceleration Results BWFC:

ly t

10:00 a.m.

Pin Puncture Analysis

-BWFC 10:30 a.m.

Buckling Analysis BWFC'

{b 11:00 a.m.

Open Discussion.

All-Y a

?

i s

h i

- I

,J

o O

O I

t t

i B&W FUEL COMPANY BR-100 RAIL-BARGE SNF CASK i

FULL PAYLOAD RE-DESIGN 1

L W. J. DECOOMAN

.q JUNE 3,1993 i

l i

WJD-6/3/93 E

...m m

....m

..m_,m-.m_m--_____._.___._____

w

.-.--e.

we

=

vw

-,wr.

-+.c.----

r e,-

. ii, - -

O O

o DESIGN OBJECTIVES e

MAINTAIN HIGH PAYLOAD (21/37)

REDUCE' WEIGHT (3-4% MARGIN).

3 e

. MAINTAIN SHIELDING MARGINS l

-(< 10 mrem /Hr)-

j e

CARRY NON-FUEL ASSEMBLY HARDWARE (NFAH)

SIMPLIFY-DESIGN &. OPERATIONS

~

e lMPROVE ALARA b.

N 4

6/3/93

- -.... ~

o o

o CASK DESIGN CHANGES 1

1 l

l NO CHANGE TO CASK WALL THICKNESS OR CONSTITUENTS e

.ONE.OR TWO PIECE LID WITH-DEPLETED URANIUM VS LEAD e

COMPLETE REDESIGN.OF BASKET e

REDUCED. CASK BODY DIAMETER-e SHORTENED CASK LENGTH mg 6/3/93

-e.--

e

-.m

-+

e-+

e 2--*w--w-*+-e

~

w

-**a

~v v,

9"v4

-e rn v

-ww.

<m-

=<w

< w e*w-

=

m

o O

O a

CASK BODY DESIGN 4

i e

MAINTAIN SHIELDING & THERMAL. PERFORMANCE REDUCE WEIGHT i

e REDUCE CLOSURE LID PRELOAD e

NEW CLOSURE: DESIGN RELOCATE VENT & DRAIN CLOSURES Y

6/3/93

________________________________u-________________,.

3

'O 0-

~

)

COMPARISON OF CONFIGURATIONS OLD NEW OPTION 2.3 OPTION 2.5 Itf L4 W '

'U U

W W

U,4 ii io i

i I

_I l

i

,)

I

]

L i _.

p 1.

__Jp g

g g}

g b

l fu-i

-l i

.}

l t

l l

=

i 1

e j e

[yp=

p y;

7 7

O O

o CASK WALL CROSS-SECTION OUTER SHELL SST XM-19,1.75" THK FUSIBLE PLUG OMS3

-M, s. f

/\\ !'

\\

\\'t fRETE

\\

u

  1. j

\\,

/

/

4.75" THK

[sg(

/

1 j

f

_s

\\l / \\ _l k '

/

f I l

\\I

\\l

/

\\

\\'\\

j\\\\l.

\\

'I

. lf,, \\

r g

- 7

- i\\l N

is

.b/

s

(\\\\/

s Y X

,/

j COPPER s

I

/

LEAD

\\

FINS 2.88" TH N

j y^v' NN1

/

/

INNER SHELL'-

. SST 304L,1" THK

.. m.

m.

m.

--ew=

,1_.-

~

e o

+

--v-w

--av w--,--

== --,--

w

ys.,..

. CASK LPPER RISG FLASGE PROFILE OF OLD DESIGN OPTION

}

l 1%

f

$1 f

DU SHIELD PLUG OPTION s<,.x 4

,u s

s:28:

i i

i *" "

</% \\

[St#

OUTER STEEL g,s sHett y

[l[,/

f..__ k TRUNNION

/

x lid $dkN, INNER STEEL

[

SHELL L CONCRETE LEAD.

o O

O CASK LOWER-ESD CHAWER LE AD SHIELDING BORATED CONCRETE INNER SHELL -

.}

/

-/

\\[ OUTER SHELL j

-N g\\ x<j x s s N N N

N

/

\\

\\

W N

.3)'d' 'f 't ;N f//,j',77l&'T

k?L;x n'K'i w' x x w

'N x N N'N'N 2.50 -

-=-

i e

1

+ -,

e

O O

O L

i SIDE FILL / DRAIN NEAR TOP l

l l

e ELIMINATES NEED TO MAKE/ BREAK SEAL DURING CLOSURE LID INSTALLATION & REMOVAL i

e PENETRATES SOLID' PORTION OF CASK WALL e

DESIGNED TO FACILITATE CLEARING 1

COVER PLATE SEALS SUBJECTED TO HIGHER TEMPERATURES DURING THERMAL ACCIDENT 1

6/3/93'

.l

O O

O SIDE FILL /DRAIS7 VENT XEAR TOP k

r fO

.O

.;;7,,j, g4

'O l

O$

~

" " " * ^ " " " " " " "

e, O O Op 9 ji

/'

= SEAL LID SEAL CHECK PORT DRAIN LINE EXIT

- CLOSURE LID

-IMPACT LIMITER. BOLT HOLES (32).'

BOLT HOLES (8)

.=

TOP SIDE DRAIN DRAIN COVER PLATE 4.75" DIA X 1" THK CLOSURE LID CLOSURE LID I

MATING SURFACE DRAIN LINE

/

MANIFOLD BLOCK Qx

/

r

-~

lw i,i m

/

kZ 2)

'\\

\\

l \\

/

\\

\\

CASK OD

/s' s '

N

\\

\\

\\

[

a /

,mg I-I LEAD - GAMMA StilELD BOTTOM OF IMPACT LIMITER I

I

/

%,','l,,'h / /,,,

~

l l

N f,/',,,

//'/s//

/

/, / lll '

i= i CASK lD

\\"

l l

'/ / /

g.

,/

,,/ / /

l_/

~

,[,f i_ i N

\\s l

1 % CONCRETE.

NEUTRON SHIELD

o O

O TOP SIDE VENT CLOSURE LID l

VENT COVER PLATE g

i CLOSURE LID MATING SURFACE I

fM lO g=A_-,

g[_Jh _

\\N\\Gj,0,l

~'

ll ll s

ii n'

d,

\\~_

li i

a

/

x s--4

~

~

\\

.s N

CASK OD

/

\\

s x A,, (:['M 13 f]_ _

'N BOTTOM OF IMPACT LIMITER

' NN\\

\\

\\ x,x \\

e CASKID

,f s

  • --/

.-N' 7

\\x.

/ /f,5)

/

J'pf

.</g;,',

N N 'N N N LEAD - GAMMA SHIELD x

.//

'9ff,/f, I. / \\'_ \\s)s

'h'

','?'.

- r,,.,,r i v u/ h.

\\~

Y CONCRETE f

_xx NEUTRON SHIELD s.

.u.

CLOSLRE LID SEAL CHECK PORT z

f CLOSURE LID I

CLOSURE LID i

MATING SURFACE I

CHECK PORT i

f y

k_

I i

m l

l m

i 1

l

)

U [,-d CASK OD x

<x r/.'MI

)

BOTTOM OF IMPACT LIMITER _

'\\\\

3;:g '

'l_

CASKID

/ q

\\.

xQ

'; >Ny 4

l-

\\y s

. LEAD - GAMMA SHIELD

( [< s a,,. /,',/.k/g -

~

\\

\\

CONCRETE l --

NEUTRON SHIELD

=

..~

o O

O BASKET DESIGN e

. WAFER BASKET DESIGN

't e

21 PWR/37 BWR PAYLOAD e

REDUCED WEIGHT e

' MAINTAINS SHIELDING MARGINS e

SEALED & EASIER TO DECONTAMINATE e

ELIMINATES REPLACEABLE FUEL CELLS e

CARRIES NFAH 6/3/93

o o

o j

21 PWR BASKET CROSS-SECTION i

L OLD l\\EW 1

e[

x 6 %_

. ::::#Rm n

o

'y o o

o

'x e

lo

-0LlO

- O O

. O.

O.

O

/

1:.r o

D; O.

10

O:

O-O

6 O^

O O

\\\\

~ OL 0

\\'

O2 LO-

10--

)l l

\\\\

1)

\\' - O Oi

- 0

, 0:

O

'/

N'

[{

lx l

.m-

..m.-

.. m.

.m -m A-.mu..m um.v

-w w wi,

"-,3-w w

v

++

w--

..~+w,,.*

-w.-

w-~*-<,, - ~ - -

-

  • Er'u -r

_-,___1____m..

.j 2h k

e C

s

.;,-q

[

\\.

t

)

\\.

b/,

l_

I I -

I s

M.F

"MW 4

O ew

- s i

i O

N 41 cn k

g

>====

dSi x

N s

r h

7 w

I

/~' ~

n v

e N

x

(

NQ O

it l

d c

S 2

is.

13

[

[-H N

~]_s 7

Z I

f g

a y;

cn G

4 tg,.

e

~

Y#

$M l

Sg3

{d 1

~

'3 si

'l h

h4 1

~~

R' s ~T t

ut'l o

Y 0

i

L.

1 N.

y k.

[a tv g/.

i

.(-

21 PWR BASKET CROSS-SECTION w

f--- 57.79 BASKET OD

' !"#rL"s""A*Jagitat MATERIAL: SST TYPE 304L

/

1.00* THK COVER PL.

s I

\\

/

pm

  1. o e

M>-

"*"" "" \\,4 6

7

'[ //

I

  1. "s" 9.685 TYP. PITCH N

111 TO O

4F O

/'j I

1 id

."TJne%,ve.

a

/,

G g.

= 7" ext a

@~ -O -G-

- 7

[s/-seAcem-Areas

\\q

\\\\ o o

o

= aM We m 4 THK

\\

NEUTRON ABSORBER

. /

\\

. "THKro LONG ERIMETER, fj

- 0.50 THKNS AT INTERIOR

o O

' BWR BASKET. CROSS-SECTION 1.00" THK COVER PL 57.79 BASKET OD M E lAL T$

E 304L

. fA':

/

O O

O

'xg/ /

Ag't:(a N'

DRAIN HOLESm N x OOo O

f

'p 7.036 TYP. PITCH f,,f

/ b 'O o i

O O y.o A'

A A'

/T A

A A

f 6

S N SID E,

\\

%2 iaarJAaa*4k OOOO O

LO O- :2 ar

-O O 0 d O

?#

SPACER WAFERS

(

AL OY d61-T,' 4" THK

^*

C::W A

UM.

TES

' 0' 5.

THKNS A NTE R

~.. -.

o O

O QUARTER-SCALE IMPACT LIMITER DROP TESTS i

' PURPOSE

~ ASSIST IN DESIGN OF IMPACT LIMITER SUBSTANTIATE LOADS-USED IN ANALYSIS I

.h h

6/ 93

O O

Q i

i DROP TEST FACILITY i

DYNAMIC TESTING INC.

IN RUSTBURG, VA -- TEN MILES FROM LYNCHBURG L

L

. FACILITIES a

i 75 TON, STIFF-LEG DERRICK' CRANE TARGET PAD 8 FT. BY.10 FT. BY 4'FT. THICK REINFORCED CONCRETE 1 1/2:IN. STEEL' COVER-PLATE TOTAL.WElGHT - 53,000 POUNDS 9

80 CHANNEL: DATA ~ ACQUISITION SYSTEM n

.HONEYWELL DIGITAL RECORDERS-Vanes 2 -

6/3/93 4

a,..

.. =

0 TEST 9RTICLES o

1 1

1/4 SCALE CASK STEEL CYLINDER MODELING CASK SIZE AND WEIGHT GUIDED FREE WElGHT INSIDE TO SIMULATE PAYLOAD l

4 i

1/4 SCALE IMPACT LIMITERS STAINLESS STEEL SKIN (1/4 SCALE)

ElGHT MOUNTING BOLTS (1/4 SCALE) i WOOD ACTUAL DENSITY AND MOISTURE CONTENT (BALSA AND i.

REDWOOD)

P, I

LIFTING YOKE ADJUSTABLE TO CONTROL.SLAPDOWN ANGLE.

SINGLE EXPLOSIVE BOLT FOR RELEASE 4

i

- Vames 3 6/3/93-

..a..

.-1 a

. -. -..2-mA-

+-i-avd--

w wW4e%'

w' v

vder--"wi'=

w m'

w-

'tr 1e e-e w

tv-4

=-

rw

.,_g e

a A

m.

.J n wa-4.

4 s

e e--t

.~ w a 4.-e.

..2-64 a

a DROP TEST SETUP i

i O

1 4

5

?

ACCELERouCTERS P

b Al'

  • 2 C2 %

T

,~g I

N C UulTER I UulTER II O

t t

30 +2" PLUMB UNE

.o onop HEicHT t

b TARGET PAD p

o L%%'R%'33 r

- I O

{

Varnes 4 6/3/93..

. I i

,1

TYPICAL RESULTS 1

f%.

/

\\

\\

)

N,_/. -

t P

e August 29,1991 Test. Slapdown (7 Degrees)

Conducted by Dynamic Testirig. Inc. at Rustburg. Va.

<se.e ;i 6

i Gauge C1, l' Impact j

3..,, :

Gauge B1, Cask CG............ :

l-Gauge A1,2d Impact

[

i zee.s l/\\

l i.%

~:

5 ges.g

-5

/k han n.. _

=

-s....

/qy

\\g,v,/ V-v~ ~.

,n i

(

c

.1, 4

-1ee.a b

.l-l.\\,.s i

~

-see.e F

=

~

.. L.

,.. L.

a TIME

.i Time history of laterial merrinations.

Filtered at 1,500 Hz low pass.

Gauge Peak level Tin.e C1 218 g's 6.8 ms t

B1 219 g's 10.8 ms Al 244 L*s 13.6 ms~

~

1 a

h 4

Vames 5 6/3/93

'I i

3 A

J P

,['

?~ W

-e x

.,w m

)

y s

~~

j s

g

\\

j h

a:;w, ;

a 9

E??$ 'h3 ' ef*.,se* Y.

  • a 2~

.... a;D.W, ~.

  • * $~h -

~^ =. c ~-

~

. :13 :E

~-e,.

~

~ ~.,,..,_ ~ g *ggyy

,~.

f' _,.

~

w~

AUGUST 29 SLAPDOWN I

Pretest Side View Rigged at 7 Degrees 1

..a 44_-.-

__=--

-4 a.--a

--a..

__a-eas-a----

h

--aam

._wmas_a 4

d--

-_w6*aa i

-m aira_.,_m

,_a.,m,,.

a 2A__g.

lam.ma a.a.-

2

.a m

uma 5

i I

i i

4 l

'A 4..'S

,7. MQp A\\s l'

~

,. c. ~. -

" f x9 -

a ;

't i

, t/4.,

1

_ -4:

j p

l k-i

/

l w

i s

1

/

l

/

~

l l

l i

l l

l i

I i

I, I

l i

i i

l l

l l

.. m.-

.d1_

a

.a a-s.A_a.._Am-..A 2

AAa A

a_

4 ;-

A2J.-mu ho--

A

.=_am.

.mL*es.m h_m u-

-we.

t i

f I

0 h

Y -.

f.

Q ;> p%-

l

  • j,

~

l ffi:

a p

-o

).

7' h

/A7 wgANM.

~

7

~

,m.

m l

/

a r

f 1

i i

I P

i l

l l

l l

r

,-e

-___________.____..._----,---.--~~-v--

,,_aA a

s a

w4uaaaa

,,+

aAn4 e.,

.-6, omA.

a-K..

nade,

gn.m

,m m.a-m,-

w nes--. maw

=---a

- _,, - - -. - - - - - ~ - - - - - _ _ - - - - -,. _ _ -

E s

i i

l 1

h 4

e 9

-3 g

J l

e Q

l l

i i

\\

l i

1

. e

==

f s

=

2 i

b m

4 s

4 i

I a

4 i

i i

)

~

J 4

i h

i g '

\\

l l

l l

l l

n 1

l

.ma l

.I l

1 I

l l

I I

i 1

I --

m a

O O

O l

BR-100 100 TON RAIL / BARGE TRANSPORTATION-CASK f

STRUCTURAL EVALUATION MAHENDRA K. PUNATAR 4

Presentation To NRC Transportation Branch June 3,1993 T

6/3/93 1-i

O O

O OUTLINE i

~ PUNCTURE

  • THICKNESS TO RESIST PUNCTURE SAKAMOTO'S NELM'S SCANS COMPARISON OF RESULTS BUCKLING e ANALYSIS e RESULTS e SCANS ANALYSIS:.

e COMPARISON OF RESULTS e CONSERVATISM IN ANALYSIS GEOMETRY AND END FIXITY ANALYSIS INPUT i

6/3/93

...s.

BR-100 CASK VESSEL

,1 !

1I i

li g

k u

@u

..(

j

).-

r :

m-l

,?

i e

I, l

l 1"

t 304L l

2.875"t Lead

---4.75" t Borated l

Concrete

-1.75" t XM-19 I.

- l l.

L L

k i.

i

' I G

3"

.t F304L

  1. y i

g, i

if 3"

t Lead

"" i

4.25"t F304L 3'

6/3/93

~

O O

O PUNCTURE METHODS 1

D SAKAMOTO 1974 EMPIRICAL EQUATION BASED ON EXPERIMENTS l

STATIC AND DYNAMIC TESTS l

PROTOTYPE CASK' AND SCALE MODELS

]

NELMS 1966 EMPIRICAL. EQUATION BASED ON EXPERIMENTS STATIC AND: DYNAMIC TESTS PRISMATIC AND' CYLINDRICAL MODELS-

.i SCANS l

BASED ON SAKAMOTO, NELMS AND ANALYTICAL RESULTS BASED ON FLAT. PLATE - CONSERVATIVE ADDED SAFETY FACTOR TO INCREASE CONFIDENCE MKP 6/3/93

O O

O PUNCTURE 40 INCH DROP ON.TO A 6 INCH PUNCH SAKAMOTO'S EQUATION :

L E~

t d

r 6

4

=

(a + 3

+ 'y

+0

)

t +" d N a

D D

d B

I a, B, y, 0,6, e, [and 11 Constants l

E - Puncture Energy = -Weight x Height ob - Ultimate Strength t

- Minimum Thickness Needed i

D -' Curvature. of Cask Outer Shell d

. Punch diameter r -- Punch Edge Radius Side Wall XM-19 Minimum t = 1.07"'. Design 1.75" Bottom Plate 304L-Minimum t = 2.47" Design 4.25" 6/3/93

O O

O PUNCTURE 40 INCH DROP ON TO A 6 INCH PUNCH i

NELMS EQUATION 3'

T=

( W / Su )

W

=

Weight, Ib Su

=

Ultimate Strength, psi 4

4 Side Wall XM-19 Minimum t =

1.70" Design 1.75" Bottom Plate 304L Minimum t =

2.48" Design 4.25" 6/3/7 i

. m-

-e s

.-=m.--

e-+e w

=

e-

  • -.t-,'

4

O O

PUNCTURE

40. INCH DROP ON TO A 6 INCH PUNCH WALL THICKNESS in inches MINIMUM WALL-THICKNESS DESIGN SAKOMOTO'S NELM'S SCANS SIDE WALL XM-19 1.75 1.07 1.70 2.56 BOTTOM PLATE 4.25 2.47 2.48 3.11 l

F304L 1

O O

O CONCLUSION PIN PUNCTURE BR-100 CASK ANALYSIS MEETS THE CRITERIA OF e

1 SAKAMOTO'S AND NELM'S DESIGN WILL BE VER!FIED DURING PIN PUNCTURE e

TESTS MAJOR DIFFERENCE BETWEEN SCANS AND BR-100 e

ANALYSESIS SCANS - USES FLAT PLATE 8

6/3/93

O O

O BUCKLING ASME CODE CASE N-284 l

e LINEAR BIFURCATION ANALYSIS i

j

o. REDUCED BY CAPACITY REDUCTION FACTOR-I

- EFFECTS OF IMPERFECTION, 1

NONLINEARITY IN GEOMETRY BOUNDARY CONDITION 1

e PLASTICITY REDUCTION FACTOR-

- NONLINEARITY IN MATERIAL i

saw 6/3/93 i

l

. ~

CASE-N-284 Buciding CASES OF ASME BOILER AND PRESSURE VESSEL CODE

(

1800

SUMMARY

The following flow chart summarizes the rules of this Case to aid the designer in using these rules. The containment shell must also satisfy all other applicable Code criteria.

Step 1: Perform static and/or dynamic analyses for each specified loading and compute stresses in accordance with -1300.

I l Step 2: Combine stresses for each Service Limit to determine the stress components, af.

l Step 3: Multiply the stress components of Stsp 2 by the proper safety factors of -1400 to obtain the buckling stress components of

  • FS i

Stop 4: Calculate capacity reduction factors, af, for each stress component of Step 2 for local buckling of each panel and for overall instability as given in -1500, h

Step 5: Calculate any applicable plasticity reduction factors, nf, per -1600 for the buckling stress compo-nents from Step 3.

I Step 6: Compute amplified stresses for the imperfect shell by dividing the buckling stress components of Step 3 by tha espacity reduction factors of Step 4, to obtain the elastic stress components af,.

ai, = al* FS/a; t

Step 7: Divide the elastic stress components of Step 6 by the proper plasticity reduction factors of Step 5 to O

obtain the inelastic stress components, afp.

Oip = OlsIni l

Step 8: Determine the buckling evaluation approach consistent with the vessel design and method of analysis.

See ~1700.

A 4

4

- 1710

-1720 or -1730 Step 9:

Step 9:

(a) If the total combined stresses of Step 2 include (a) Perform axisymmetric shell of revolution or any discontinuity stresses, follow the procedures of three<limensional thin shell buckling evaluation

-1711.

per -1720 or -1730 for each set of stress compo-

. (b) Repeat Steps 2 through 7 for stress components nents, af, from Stop 6.

corrected per (a) above.

(b) For sech set of stress components where 94 or (c) Calculate classical unlaxial buckling values per 94g is less than one, set opp = 0 and perform buck-

-1712.

ling evaluation.

(d) Check elastic and inelastic relationships of (c) For each set of stress components where as or

-1713.

nog is less then one, set ogy = 0 and perform buck.

(e) Sire stiffeners per -1714 ling evaluation.

I

( All interaction relationships satisfied? [y** / Values of Ac for all food conditio for local buckling and 1.2 for stringer buckling or

\\ general instability?

o Check localized buckling for concentrated loeds on the shell and provide local stiffening, if needed.

Stoo)

No

--l Modify design - Start with Step 1 h V

,e 10 6/3/93

L ALLOWABLE BUCKLING STRESS ASME CODE CASE N-284 Hypothetical Accident Conditions Compressive

@. -20 F

@ 250 F

Stress psi-psi Inner Hoop 14,900 11,715 Vessel

-Axial 20,360 14,895 7

6/3/93

.e

.,n

O O

O j

CASK VESSEL Two-Dimensional Structural Analysis l

DROP 1-Ft & 30-Ft

.[yf Quasi-static Analyses iiiii Bonded & Unbonded Lead j jjjj End Drop - Closure end l jjj End Drop - Bottom End 1

I Ill IEEEBiii immiiia EdiE!5 Vessel Axisymmetric Mathematical Model

,,lj ABAQUS

o O

O INNER VESSEL STRESS 30-FOOT END DROPS

^

1 BONDED AND UNBONDED LEAD

  • TOP AND BOTTOM END DROPS AXIAL HOOP psi psi-END DROP-

-3,784

-9,728 ANALYSIS

_3,619

-9,853 N-284 BUCKLING ALLOWABLE

-14,895

-11,715

@ 250 F

6/3/93'

O O

O CONSERVATISM IN THE ANALYSIS l

GEOMETRY e

END FIXITY (Factor of 3.2?

j l

e STATIC YlELD PROPERTIES FOR 304L (Factor of 1.345 @ 0.07 in/in/sec) e FRICTIONLESS SLIDING BETWEEN LAYERS e

DAMPING NOT CONSIDERED m

i CO 4

o g

- t i

- '\\j QCE i

m i

N-W<

s U)4 o

oO e-I CD m

f-N I

4,

'p-

_.. a b) t

4-.6-.+-.4._.+.

Ng s i e i i e a i e i i :

o--*---+->-.w.

f' k

I I I I I I p

\\

f,* '

g i

i

.-,+.%,.%,.

A,.,

. i

' i i i e i e i i e i i i

e i i,

.->+.%.i

-***6----+at---+---4.-.w._:

.+,_,,.%.

I I I I I I i i i I t

1 4

l l

6 l

g g g I

8 6 t i e i t i s a g g g-g g W's _ j

'8k - - *O *+-----+-4---+-.4--.+-4..-

..->+.

,,4_

8 8 8 8 I I 3 I t t I i t e i i i I -

_. 3p 1

EIER m

m e

6m ggg g

numa n,,

,_n. u _ n' x

--9,c /5nt;,979;,,7//,,,4;,

97/m yz5mw..

...:.,w:.g n

lii

.E llll Sfb d

cCC dM Adh

<ee O

C 1.(

o O

O SCANS ANALYSIS l

e 30-FOOT END DROP UNBONDED LEAD INNER VESSEL STRESSES - psi l

AXIAL HOOP BUCKLING 8 MASS

-10,661

-33,915 LIKELY-JOINTS 20 MASS

-15,760

-48,530 LIKELY JOINTS.

6/3/93

o O

O LEAD DYNAMIC MECHANICAL PROPERTIES 4

}

CHEMICAL LEAD i

oy YlELD STRENGTH - psi

-40 F

70 F

300 F

DYNAMIC 11,200 10,300 6,100 Ref:

ORNL-NSIC-68 Cask. Designer's Guide ORNL'TM-681 A Guide to the Design of Shipping Casks ORNL-TM-1312, Vol. 6 Impact Testing... Lead Shielded Cask Model

";7 6/3/93

...r..

o O

O L

LEAD DYNAMIC YlELD STRENGTH i

l Dynamic Flow Pressure

=

PE / AV (ORNL-NSIC-68)

Where PE = Potential Energy l

AV = 6 A Volume. Change A

j Dynamic Flow Pressure = PE / 6 A c-----.

n U

=a e - V Strain energy y

Where a

= Yield Strength (E-PP) y e = 6 / L Total Strain L

V = L A Volume of Material Strained

,.U

= a 6/L - L A

~

y l

=a6A y

Since

.U = PE, a Dynamic Flow. Pressure

=

y 6/3

E c

s m-

+

'h Q

.M 35 g

'e v

,~

2m q'

g

?

R p

o t

i "Q

w3 T3 4

4 1

4m e

M e

x a

4

~

UE(m I

h 2

h D

7 x

T M

4 02k4 3

e 4 4 4C A

6 l

l l

O o

m l

l m

g O'CU y

a o.

Ir

's 5

'E D

' t "x \\

'o D'i

  • v B\\"

\\1 p\\.

~ e ma,

\\

e m

s.

'\\

-si g

d b

" M

.s,'S s e, "* 0 '\\

t ' 4

.C, G 4-

-o 4

t S

-g a

  • h o"xk \\

'i

~

6 d

'D.i T:i o,; \\ \\

g

', \\

3 E

o-a em 1

% \\,\\

i\\

_ %j'

@ l'"'",

g2,,

o M CU

', \\ \\

i\\s i\\

s o.

5 e>

o s

. \\ t' CU m

\\

no

\\

o n

6m*

g

\\

\\".n'

- o ';

Mc 11 i

.o

-

  • x,.\\ *.',

y

"*.N Q

o

-M ce s

= o\\*

W*4

_ t

=

ZV y(

o o

w o

4g N o, T [

6 m

Og n'

W.O lo i

o

,a e

a a

.o M

Q

,M C,

k b

E 2.50 U) u)

-!+

uA 3

(t3 - (13 a) =

-g J cts g-

-(

CONCLUSION - VESSEL BUCKLING e

BR-100 CASK ANALYSIS IS VERY CONSERVATIVE l

o BUCKLING IS UNLIKELY DUE TO GEOMETRY i

CONSTP.'JCTION e

DESIGN WILL BE VERIFIED DURING DROP TESTS e

MAJOR DIFFERENCE BETWEEN SCANS AND BR-100 ANALYSIS IS DUE TO LEAD PROPERTIES L

BR-100 CASK ANALYSIS LEAD PROPERTIES ARE BASED ON ACTUAL DROP TESTS 6/3

- -

Retrieved from "https://kanterella.com/w/index.php?title=ML20045C740&oldid=4526935"