ML20076H356

NDE of Fort St Vrain Fuel Element 1-2415

ML20076H356
Person / Time
Site:	Fort Saint Vrain
Issue date:	05/17/1982
From:	Saurwein J GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
To:
Shared Package
ML20076H347	List: A16829, NDE of 54 Fuel & Reflector Elements from Fort St Vrain Core Segment 2 ML20076H345 ML20076H356 ML20076H396
References
906505, PED-81-2200, TAC-57625, NUDOCS 8306160545
Download: ML20076H356 (9)

Text

-

g qA 1485(REV.11/80) (PED-81-2200)

ISSUE

SUMMARY

TITLE: NONDESTRUCTIVE EXAMINATION OF FSV FUEL ELEMENTO R & D APPROVAL LEVEL 5 1-2415 la DV & S O DESIGN OlSCIPLINE SYSTEM 00 C. TYPE PROJECT 00CUMENT NO. ISSUE N0/LTR.

N 18 RGE 6400 906505 A QUALITY ASSURANCE LEVEL SAFETY CLASSIFICATION SEISMIC CATEGORY ELECTRICAL CLASSIFICATION I SC-1 CAT.I N/A PPROVAL PREPARED ISSUE

, ISSUE DATE DESCRIPTION BY S\

? :'A ENGINEERING QA PROJECT

n. m a _,

$dA J.J. N.E I.B. Scott Initial release from n StanYI[eII Pettycord originating project No.

gy1y g ( fam*u -

6415 020 204 S//7/&L l W. A. 3.f r. 32 imonfQ 5 }gL.

[

C.E.M-L Interface Assurance CONTINUE ISSUE

SUMMARY

ON GA FORM 1485-1. NEXT INDENTURED DOCUMENTS

. ,, , e 903909 NON-CONTHOLLED COPY VERIFY ISSUE STATUS WITH DOCUMENT CONTROL l

PRIOR TO USE I

REV SH l REV SH 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 REV SH 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 l

8306160545 830602 PAGE 1 0F 9 i PDR ADOCK 05000267

( P PDR

GENERAL ATOMIC COMPANY GA-1484 NONDES'IRUCTIVE EXAMINATION OF FSV FUEL ELEMENT 1-2415 Document No. 906505 I"'

A The purpose of this report is to document a specific result of the sur-veillance of FSV segment 2 core components (Ref. 1), the crack observed in fuel element S/N 1-2415.

One-hundred-five fuel and reflector elements irradiated in core se gment s 1 and 2 of the Fort St. Vrain High-Temperature Gas-Cooled Reactor (h"111R) have j been visually and dimensionally examined in the Hot Service Facility at Fort E

St. Vrain (FSV). The elements, (54), from segment 2 were examined in April

.$ 19823 the elements, (51), from segment 1, in July 1979 (Ref. 2). All examina-tions were performed as part of the Fort St. Vrain Surveillance Program spon-fe,, sored by the Department of Energy.

E f Among the 105 examined fuel and reflector elements, segment 2 fuel ele-f ment S/N 1-2415 is unique in that it was observed to have a clearly visible crack. The crack is located in the center of face B and extends the length of I the element (Figs. I and 2), running parallel to and into the adj acent coolant E

hole (Fig. 3). Attempts were made, (using alcohol), to determine whether or g

. not the crack extends to the fuel holes under the dowel, but were inconclu-

,s sive. The preirradiation inspection reports indicate that the block was not

,k cracked prior to insertion in the core, and there is no record of any damage

! having been done to the block during handling (Ref. 3), so it must be assumed z

that the crack developed during irradiation.

Element 1-2415 was irradiated in region 8, column 5, core layer 6 (third layer of fuel elements from the top of the core). The core location is shown in Fig. 4. The element-averaged f ast fluence was approximately 1.5 x 1025 n/m2 (E > 29 fJ)lrIliR and the time-and volume-averaged graphite temperature was around 6500C. The ranges of fast fluences and irradiation temperatures for all of the examined fuel elements were 0.3 to 1.6 x 1025 n/m2 and 400-7500C, respectively.

The block average axial and radial strains for element S/N 1-2415 were 4 measured to be -0.34% and -0.20%, respectively. The maximum bow was 0.43 mm.

Page 2

GENERAL ATOMIC COMPANY GA-1484

, TITLE: -

NONDES'1RUCTIVE EXAMINATION OF FSV FUEL ELEMENT 1-2415 Document No. 906505 issue A (Bow is here defined as the displacement of the side face relative to a straight line connecting the top and bottom of the side face. See Fig. 5)

This element had the largest bow of any of the examined element s. However, several elements were bowed nearly as much and had comparable axial and radial strains. The axial and radial strain distributions for element 1-2415 are shown in Fig. 6 and Table 1. The maximum bow for each side face is also shown j in Fig. 6.

E e

8

= REFERENCES

.c h 1. SAURWEIN, J. J. , Test Specification for the Surveillance of FSV Segment E 2 Core Component s' ', General Atomic Company, Document No. 906399, March j 29, 1982.

5 5

2. MILLER, C. M. , and J. J. SAURWEIN, Nondestructive Examination of 51 g

Fuel and Reflector Elements from Fort St. Vrain Core Segment l, Depart-j ment of Energy Report GA-A16000, General Atomic Company, December 1980.

h

.5 3. Personal communication with Chuck Fuller, Public Service Company of Colorado (PSC).

.3 i

(

Page 3 l

GENERAL ATOMIC COMPANY GA-1484 ,

, TITLE:

NONDESTRUCTIVE EIAMINATION OF FSV FUEL ELEMENT 1-2415 Document No. 906505 issue A l

l

. l'

' ~

l' .' l~_

l .

7 .N

=

},

j. ~-

'-M

~

l j E

a . . ,

l t 5

! E l e i!

8 .

5

>; .h. e- '

g .

c 2  :. .,

u .,

i l

. j._...

.h ._;f[tw. .

{T _

. -_t._ _ ._

l _

C .r.-

.g _ ;. m /.

2..  :

3 ,

2 O .,r

.6- -

-1.

i

. . 2 3

Fig. 1 Photograph showing crack in f ace B of fuel element  !

1-2415 l

Page 4

GENERAL ATOMIC COMPANY GA-1484 i

I NONDESTRUCTIVE EIAMINATION OF FSV FUEL ELEMENT 1-2415 i Document No. luue

906505 A l

t

, e

, t . . .; .

4.. .

~,

,., [. gy :%y ev ..

E '

s. '-

n .

E 2 *

8. <

, .g...-.

5 s.

e

.3 5

$' Pig. 2 Crack in face B of fuel element 1-2415.

j Crack extends through bottom chamfer.

I (Magnification X1/2)

E

_8 5

N...T .

n, 8

's .~

o /_

z .

' p ., , -

.., ,.n ,

,g. .

1 ,

,3 . 4.

Y < , , .. .n Fig. 3 Photograph showing crack extending into the coolant hole between the dowel and the edge of the block. (Magnification II)

-> i Page 5 '

i GENERAL ATOMIC COMPANY GA-1484

, TITLE:

NONDES'IRUCTIVE EIAMINATION OF FSV FUEL ELEMENT 1-2415 Document No. 906505 issue A N'

s n .

Wy '-

, , 8.7

"': : NUE'*- h *

R .%

,  % 7  % _

h f Q ,

1. '2N*w

,om ~u,

\

t,^%.i

\\

QsS) 33 .

sT /

\

7 2 J r g9 *

// 22 g ,

y" eM@

~i

u 7 a

,- 4

\Q\ p~ \ t u1 A

),

g7 i

i

(

~

_ _. h A;/C;L 'lL , ,, .d._ _

Ilr _

• I'!

$  % \\

zc - #

.'~"

>.s -

sn ~

~s'. n.1 ~ . 2~~0 .o .

h = <,(

~ , ' . n sl' E

E -

. . ht

[ff si

'?

/ is /

5

[ 6 t

f/ II

/

A 26 \Q (gy/

$ ifl.% 4. .

\, .  %~  % g\OQ.g'

' ' 'Ey

• i 1 ' 4 D f[ bj['

.E -

3o ..-

su' f is' 4/  : // 25 i- '

E  % i \\ 'd  % \\' .

E ~ '%,\ '

n .&A \\ ~d  %.\u,-:~lt{'

2 -

o .

)  :+\

i M u. /

hf i- _ i>. /

-.. . ' . {' ,

Kij i

• Fuel element 1-2415 Region 8, column 5, active core layer 3 Fig. 4 Core location of fuel element 1-2415 Page 6

. . GENERAL ATOMIC COMPANY GA-1484 TIT W

-> NONDESTRUCTIVE EXAMINATION OF FSV FUEL ELEMENT 1-2415 Document No. 906505 issue A Top chamfer

\ L

/ \

i I

i

9. I E l E

.E I

E i

.c 5

C I e

.E 5

2 I

.9 2-l

\

E 2 j o Bow i-

\

I l

"5 \

.e 3

we Z \

Bottom chaefer

/

Fig. 5 Bow is defined as the displacement of the side f ace relative to a straight line con-necting the top and bottom (below and above the chamfers) of the side face.

I Page 7 g_ __.___ _ __ - - - - - - -__ _,x-_ me__d

GENERAL ATOMIC COMPANY '

GA-1484 NONDESTRUCTIVE EXAMINATION OF FSV FUEL ELEMENT 1-2415 Document No. 90650S ,

Issue A Face E Dowel Lo .: = -0.33 == ,-

5 4 3 2 1

-0 257 -0.254 -0.254 -0.247 -0.241 ,7 Face D 7 Bow = -0. 20 m Bow = -0.15 m 7 8 9

-0.2 3 1

-0.273 -0.266 i.276 11 16 -0.276 13 -0. 02 10

-0.292 14 -0.298 12 -0.299 j -0.292 -0.305 \ '

E 17 18 19 20 21 22 5

S -0.318 -0.314 -0.330 -0.324

[-0.298-0.314 27 26 3 /

t / -0.337 -0.311 50 51 52 25 24 23 ,

@ -0.343 -0.359

.y -0.340 -0.327 -0.330 -0.334 g

53 34 2 -0.343 -0.340 49 48 47 46 45 44 d -0.353 -0.372 -0.388

-0.366 -0.356 -0.353 5

5 41 g 39 43 E 37 -0.356 40 -0.356 3 -0.375 38 -0.375 42 -0.338 Face C -0.359 -0.385 Face A

.j Bow =

36 4 33 Bow =

" 91 -0.411 0.28 m i $ -0.388 -0. -0.$01 l 'ii i 5 z 2, 31 32 28 29

-0.427 -0.423 -0.430 -0.427 -0.433 NOTE:

Bow = 0.43 m Pceitive bou - concave.

Negative bow - convex.

Face B f All strains (6E/E) in %.

( Element average axial Location of strain = -0.337%.

crack l

Fig. 5 Measured axial strain and bow for funi element 1-2415 Page 8

__s

GENERAL ATOMIC COMPANY GA-1484

, TITLE:

NONDESTRUCTIVE EXAMINATION OF FSV FUEL ELEMENT 1-2415 Document No. 906505 Issue A Table 1 MEASURED RADIAL STRAIN FOR FUEL ELEMENT 1-2415 Distance from Radial Strain (AX/I)%

Bottom of Block (in.) Faces A-D race s B-E Face s C-F Average j 1.25 -0.126 -0.091 -0.120 -0.112 E

5 7.25 -0.171 -0.145 -0.155 -0.157 il 13.25 -0.205 -0.176 -0.190 -0.190 j

5, 19.25 -0.230 -0.204 -0.219 -0.218 f 25.25 -0.265 -0.215 -0.247 -0.242

~30.25 -0.274 -0.236 -0.261 -0.257 8

h Block Average -0.196

.E E

.2 8

.5 E

.e E

+

Page 9 of9

. . _ _ ..