ML20064M741

Test Rept:Nondestructive Exam of Fsv Fuel Test Element FTE-1

ML20064M741
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Site:	Fort Saint Vrain
Issue date:	09/20/1982
From:	GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
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ML20064M711	List: A16402, Irradiation-Induced Creep in Graphite:Review ML20064M709 ML20064M741
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906599, NUDOCS 8302150630
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Text

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SUMMARY

TITLE: TEST REFORT: NONDESTRUCTIVE EZ.OiINATION OF U R&D APPROVAL LEVEL 3 E

3 FSV FUEL TEST ELFlENT FTE-1 C

S GN CISCIPLiNE SYSTEM 00C. TYPE PROJECT 00CUMENT NO.

ISSU E NO./ LT R.

j A

N 18 RTE 6400 o m oo QUALITY ASSURANCE LEVEL SAFETY CLASSIFICATION SEISMIC CATEGORY ELECTRICAL CLASSIFICATION QAL I SC-2 CAT I N/A APPROVAL PREPARED ISSUE sA ISSUE DATe DESCRIPTION BY s - 4 ENGINEERING, QA PROJECT a Wn dA 3EF20 y-rfedu

.F. Turner Initial release frem i 8P 5

[gA e//6/gs me ettycore 0

O

! Interfaced-071 CONTINUE ISSUE

SUMMARY

ON GA FORM 1485-1.

NEXT INDENTURED DOCUMENTS 904411 8302150630 830128 PDR ADOCK 05000267 P

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GENERAL ATOMIC COMPANY GA-1484 TITLE:

-"IST REFORT: NONDESTRUCTIVE EXAMINATION OF FSV FUIL TEST ELIMENT FTI-1 Document No. 906599 issue A

TABLE OF CONTENTS 1.

INTRODUCTION.

4 2.

IRRADIATION HISTORY 5

3.

TEST METECDS.

6 4.

IEST RESULTS..

7 4

4.1. Visual Examination 7

4 5

4.2. Di=ensional Measure =ents 7

4.3. Gamma Dose Rate.

8 5

4.4. Neutron Count Rate 9

.=

y, 5.

CONCLUSIONS 9

=

j 6.

REFERENCES 10 a

I LIST OF FIGURES

.3$

-j 1.

Local point numbering - SURVEY code analysis of FSV FTE-1 11

=

5 2.

FSV FTE-1, side face A.

12 C

3.

FSV FTE-1, side face B.

13 l

5 4.

FSV FTE-1, side face C: discontinuous vertical scratch

=

i starting near top center and extending devn face.

14 5

li 5.

FSV FTE-1, side face D.

15 3

2 6.

FSV FTE-1, side face E.

16 7.

FSV FTE-1, side face F:

short vertical scratch near the upper left corner 17 8.

FSV FTE-1, top surface.

18 9.

Examples of discolorations observed on the top surface of FSV fuel test element FTI-1 19 10.

Measured axial strain and bow for.'SV fuel test element FTE-1 20 LIST OF TABLES 1.

Ti=e-averaged graphite irradiation ta=peratures for FSV FTI-1 21 l

Page 2

l

t,'

GENERAL ATOMIC COMPANY G A-1 "84 IIM

+

TEST REFORT: NONDESTRUCTIVE EXAMINATION OF FSV FCEL TEST ELIMENT FTI-1 Document No.

906599 A

LIST OF TABLES (Continued) 2.

Fast neutron fluences for FSV FTE-1 21 3.

Distance-between-fiducial-hole measurements for FSV fuel test element FTE-1 22 4

Measured radial strain (from distance-across-flats measurements) for FSV fuel test element FTE-1 23 5.

Coolant hole diameter seesure=ents for FSV fuel test i

element FTI-1 24

=

6.

Distance-between-coolant-hole =easurements for FSV j

fuel test element FTE-1 25 7.

Calculated and measured strains and bow for FSV fuel i

test element FTE-1 26

's

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l Page 3

GENERAL ATOMIC COMPANY

~

GA-14&4 TITLE:

TEST REFORT: NONDESTRUCTIVE EIAMINATION OF FSV FUIL TEST ELEMEN* FTI-1 Document No.

I" 906599 A

1.

INTRODUCTION Fuel test element FTE-1 is one of eight fuel test elements (Ref. 1) inserted into the FSV reactor during the first refueling.

The element was irradiated in core location 25.07.F.06 (region 25, column 7, core layer 6) for 189 effective full power days (EFFD).

As shown below, there were a number of sajor differences between FTI-1 and regular FSV fuel elements.

FTE-1 Regular FSV Fuel Elements 4

3 Graphite (grade)

H-451 H-327 E

Fuel UC TRISO/Th0 TRISO (Th,U)C TRISO/ThC TRISO 3

3 2

3 s

Curing process Cure-in-place Cure-in-bed j:

(fuel rods)

-]

A nondestructive examination of FTE-1 was perfor=ed in the Hot Service Facility (HSF) at FSV on April 16, 1982.

The examination included:

S A visual inspection for corrosion, cracks, scratches, and

';?

other abnormalities, i

E

.2o Di=ensional measurements (with the =etrology robot) e

=

=

.5

- Across-flats dimensions n

ji

- Element length

- Coolant hole dia=eters z

- Distance between coolant holes

- Distance between fiducial holes

- Bow l

• Gamma dose rate and neutron count rate measurements.

• Cycle 2 was from May 26,1979 to May 13,1982.

l Page 4

GENERAL ATOMIC COMPANY GA-1484 TE TEST REFORT: NONDESTRUCTIVE EIAMINATION OF FSV FUEL TEST E!ZMENT FTE-1 Document No.

906599 Ime A The objactives of the examination were to:

Verify the structural integrity and dimensional stabill:7 of the H-451 graphite block.

• Obtain H-451 graphite di=ensional change and bow data for comparison with HTGR design code strain and bow calculations.

e Obtain a ga==a dose rate and a neutron count rate for co=parison with HTGR co=puter code calculations.

.=

E 2.

I*GADIATION HISTCRY ii

=

j The following LHTGR design codes were used to simulate the irradiation g

history for FTE-1.

5

.s GAUGE (Ref. 2) - used to calculate radial power and flux distributions g

aj for FSV cycle 2.

=

3 j

GATT (Ref. 3) - used to calculate the power history for FTE-1.

E 3

SURVEY (Ref. 4) - used to calculate the te=perature and fast neutron S

fluence histories for FTE-1 at 35 local points (Fig. 1).

The results

,e

=

l

,g

~

fro = GATT indicated that during cycle 2, FTE-1 produced approxi=ately C mere power than would have been produced by the seg=ent 2 ele =ent that

=

l l

l l

l l

l The original ther=al analysis for FTE-1 (Ref. 1) wan performed with the TREVER code. The TREVER and SURVEY codes utilize the sa=e ther=al l

odel and fast neutron fluence calculation. Bench = ark calculations have l

been performed which verify that, given the sa=e input data, the two codes l

calculate the sa=e te=peratures and fast neutron fluences.

1 1

l 1

Page 5

l GENERAL ATOMIC COMPANY GA-1184 TIT 1 TEST RFFORT: NONDESTRUCTIVE EXAMINATION OF FSV FUEL TEST ELEMENT FTE-1 Document No.

8 906599 A

it replaced. This was modeled by adjusting the appropriate axial power profiles used in SURVEY. The axial power factors for the axial locations occupied by FTE-1 were increased by 8% and the axial power profiles were renormalized. The radial power and flux distributions for core region 25 were obtained from the GAUGE analysis of cycle 2.

The perturbations in the region and colt =:n average powers caused by the insertion of FTE-1 into region 25 were small and were not considered in the SURVEY analysis.

SURVEY / STRESS (Ref. 5) - used to calculate stresses, strains, and bow for FTE-1.

These calculations were based on the irradiation conditions 5

obtained from SURVEY.

2 The time-averaged graphite te=peratures and fast neutron fluences calculated h_

for FTE-1 are given in Tables 1 and 2.

Section 4.2 discusses the results of the SURVEY / STRESS calculations.

Oe

~5 s

3.

TEST METHODS 3

=i

. =.

In addition to FTE-1, 53 fuel and reflector ele =ents from FSV core seg=ent

=

-}

2 were examined in the HS7 at FSV in April 1982. The same test methods were j

employed for the examination of FTI-1 and for the exa=inations of the other 53

.5 elements. Ref. 6 describes these methods.

E

.2

s3z

• Accarding to the GATT results, the ratio of the power generated by FTE-1 and the power that would have been generated by the ele =ent it replaced, (or the axial power correction factor, as it is called in Ref. 1), decreased from about 1.09 at the beginning of cycle 2 to about 1.07 at the end of the cycle.

The axial power correction factor originally reported for FTE-1 in Ref.1 decreased from 1.30 to 1.10 during cycle 2.

This correction factor was calculated with the FEVER code. As stated in Ref 1, the FEVER calculations overestimated the power perturbation effect of the test elements because of the boundary conditions assumed by the code. 3ecause FEVER is a one-dimensional code, it =ust assume that the column of fuel elements being evaluated is surrounded by an infinite array of identical colu=ns of elements.

Consequently, the neutron fluxes calculated by FEVER for FTI-1 were eco high since F*E-1 had a heavier fuel loading than the surrounding partially depleted fuel elements.

3ecause it is a three-dimensional code, GA*T can accurately calculate the boundary conditions, (and therefore the neutron fluxes and fission races), for the test ele =ents.

Page 6 g

GENERAL ATOMIC COMPANY GA-1484

->I

'lTLE TEST REFORT: NONDESTRUCTIVE EXAMINATION OF FSV FUEL TEST ELEENT FTE-1 Ime Document No. 906399 a

4.

IEST RESULTS 4.1 Visual Fasmination FTE-1 was in excellent condition. No cracks were observed on any of the element's surfaces; nor was there any evidence of graphite corrosion or other significant structural damage.

Figures 2 through 7 show the side faces of FTI-1.

Face C had a discontinuous vertical scratch running nearly the length of the element (Fig. 4).

Similar scratches were observed on face C of several other ele =ents and are thought g

j to have resulted during handling, possibly frem contact between the elements and a storage rack in the fuel handling machine. There was also a short vertical UF scratch near the upper lef t corner of face F (Fig. 7).

e

-u Fig. 8 shows the top surface of FTE-1.

Numerous dark markings (Fig. 9) were observed on this surface. Many of these were on top of, or around, fuel hole plugs and appeared to be build-ups of some substance. The metrology

=

1; robot was used to demonstrate that this was not the case. The darkened areas E

were found to be level with adjacent non-discolored areas. Dark markings were

=

c

.g also observed between the burnable poison holes and the adjacent coolant holes.

)

The markings on the top surface of FTE-1 are believed to have been stains caused by outgassing from the graphite cement used to ce=ent ene fuel hole plugs 2:

j in place. These types of markings were not observed on any of the other z

examined fuel elements.

No unusual features were observed on the bottom surface of FIE-1.

4.2 Di=ensional Measurements FTE-1 underwent little dimensional change as a result of irradiation.

The element-average axial strain (al/D was -0.038%, corresponding to a length reduction of 0.31

=m.

The element-average radial strain was -0.012%,

• Unlike the regular FSV fuel elements, the fuel hole plugs were cemented in place af ter the element was heat-cured Page 7

GENERAL ATOMIC COMPANY G A-1484 TITLE:

).

n37 ggpag;. NONDESTRUCTIVE EXAMINATION OF FSV FUEL TEST EL."..ENT FTE-1 Occument No.

906599 A

corresponding to a shrinkage of 0.04 mm across-flats. The maximum bow was 0.08 =m.

The axial strain was highest, -0.051%, adjacent to face 3 and lowest,

-0.022%, adjacent to face E.

Fig.10 shows the axial strain distribution as deter =ined from element length =easurements. The distance-between-fiducial-hole measurements (Table 3) indicate that the axial strain was greater at the top of the block than at the bottom. The block-average axial strains between the top two, middle two, and bottom two fiducial holes were -0.065%, -0.033%, and 2s E

0.009", respectively.

=

a As shown in Table 4, the radial strain, (as determined from the distance-across-flats measurements), also decreased from the top to the bottom of the f

block (-0.032" to 0.004%). The average radial strain determined from the coolant 3

hole diameter =easurements at the top of the block (Table 5) was -0.220%, but sj is suspect because of the small di=ensions involved. A bias of only 0.03== in j

the coolant hole diameter measurements would account for the discrepancy between

,]

the radial strains determined from the distance-across-flats and coolant hole w

l diameter =easurements. The average radial strain determined from the distance-

.=

5 between-coolant-hole =easurements at the top of the block (Table 6) was 0.028".

.e

.5 Table 7 cocpares the strains and bow calculated by SURVEY / STRESS with the e

3 corresponding measurements. The strains were consistently overpredicted, but 5

the absolute differences between the calculated and =easured values were less g

than 0.100%. Although the strains were somewhat overpredicted, the strain differences within the element were well predicted. The calculated acd measured top-to-bottom differences in the radial strain were 0.047% and 0.036",

respectively. The calculated and measured maximum across-flats differences in the axial strain were 0.043% and 0.022%, respectively. The calculated bow was 0.10 =m and the =easured bow was 0.08 :.n.

4.3 Ga==a Dose Rate At 3 feet, the gacma dose rate measured for FTE-1 was 3 3 R/hr.

The PATH

(

l ode (Ref. 7) was used to calculate the g e n dose rate for FTE-1.

At 3

(

Page 3

l GENERAL ATOMIC COMPANY GA-1484

+

IEST REFORT: NONDESTRUCTIVE EXAMINATION OF FSV FUEL TEST ELEMENT FTE-1 Document No.

8 906599 A

feet, the calculated gamma dose rate was 354 R/hr.

4.4 Neutron Count Rate A SNOOPY-type detector system equipped with a Reuter-Stokes Model RS-P6-0305-134, fission counter was used to obtain a neutron count rate from FTE-1 for comparison with MORSE code (Ref. 8) calculations. The measured count rate was 0.00112 counts /sec. (15 counts over 224 minutes). The calculated count rate was 0.00104 counts /sec.

-j

=

2 5

i 5.

CONCLUSIONS h

5.1 The structural performance and dimensional stability of FTE-1 were a5 excellent. No cracks were observed in any of the ele =ent's surfaces. There j

was no evidence of graphite corrosion or other structural da= age. The element a

underwent little di=ensional change as a result of irradiation. The element-3 Ug average axial strain was -0.038%, corresponding

• .o a length reduction of 0.31 j

=m.

The element-average radial strain was -0.012%, corresponding to a shrinkage i

of 0.04 cm. across flats.

Ae maxi =um bow was only 0.08

=m.

However, it should be noted that the fast neutron fluence for FTE-1 (NO.65 X 10~5 n/m, E > 29fJ g"

HTGR

.5 is far less than the maxi =um fast fluences that will be experienced by FSV fuel 2

9

?

n/m ) and LHTGR fuel elements (N6 X 10~5 n/m").

e

.g elements ( %8 X 10~S Si3z 5.4 FTE-1 shrank less than expected (based on SURVEY / STRESS dimensional change calculations). However, the absolute differences between measured and calculated strains were less than J.100%. The measured bow (0.08 =m) and calculated bow (0.10 c:m) were approximately equal.

5.3 Excellent agreement was obtained between measured and calculated ga=ma dose rates (358 R/hr. vs. 354 R/hr. at 3 feet), and between measured and calculated neutron ecune rates (0.00112 counts /sec. vs. 0.00104 counts /sec.) for FTE-1.

The ga=ca dose rate was calculated with the ?ATH code. The neutren count rate was calculated with the MORSE code.

Page 9 l

GENERAL ATOMIC COMPANY GA-1484 TEST REPORT: NONDESTRUCTIVE EXAMINAT ON OF FSV IUEL TEST ELDENT FTE-1 l*8 Document No. 906599 A

Verification of HTGR design code calculations cannot be accomplished through comparisons of calculations and experimental obcervations for one element. Many such co=parisons for core components which have collectively experienced a wide range of irradiation conditions are required.

The results of the comparisons between =easure=ents and design code calculations (SITAVEY/ STRESS, PATH, MORSE) for FTE-1 should be reviewed with this in =ind.

Additional comparisons between measurements and calculctions for FSV fuel elements are provided in Ref. 6.

5 g

6. REFERDICES 2

E S

1. " Safety Analysis Report for Fort St. Vrain Reload 1 Test Ele =ents FTE-1

{"'

Through FTE-8," General Atomic Company Report GLP-5494, June 30, 1977.

]

2. Wagner, M.R., " GAUGE, A Two-Di=ensional Few Group Neutron Diffusion-Depletion S

Prograr for a Uniform Triangular Mesh," USAEC Report GA-8307, General Atomic 3

g Company, March 15, 1968.

j

3. Kraetsch, H., and M. R. Wagner, "GATT, A Three-Di=ensional Few Group Neutron j

Diffusion Theory Program for a Hexagonal Z Mesh," USAEC Report GA-8547, f

General Atomic Company, January 1, 1969.

j

4. Georghiou, D. L., " SURVEY, A Computer Code for the Ther=al and Fuel 3

Performance Analysis of High-Temperature Gas-Cooled Reactors," General

,=

j Atomic Report GA-D14869, November 1978.

j

5. Smith, P.

D., " SURVEY / STRESS, A Model to Calculate Irradiation - Induced Stresses, Strains, and Deformations in an HIGR Fuel Block Using Viscoelastic Beam Theory," General Atomic Report GA-A13712, October 20, 1975.

6. Saurwein, J.

J., " Nondestructive Examination of 54 Fuel and Reflector Ele =ents from Fort St. Vrain Core Seg=ent 2," DOE Report GA-A16829, General Atomic Company, to be published.

7. Clark, S. and B. A. Engholm, " PATH - A Highly Flexible General Purpose Ga==a Shielding Program," General Atocic Report GA-9908, December 10, 1969.

8. Straher, E., et al., "The MORSE Code - A Multigroup Neutron and Gx m Ray Monte Carlo Transport Code," Oak Ridge National Laboratory Report OR'!L-4585, Septe=ber 1970.

lPage l

m

GENERAL ATOMIC COMPANY GA-1484 TRE:

TEST REFORT: NONDESTRUCTIVE EXAMINATION OF FSV ru c TEST ELEMENT FTE-1 I"'

Document No.

906599 A

REACTOR REFERENCE DIRECTION Face C

^

2 3

=

Face 3

\\ Face D

?e

~.

be

-u I

M

(

i 7

2 3

.=E E

E

.==

8

.a_

Face A Face E 8=

j 6

5 Dowels Face F l

SURVEY code calculations were perfor=ed for 7 local points at 5 axial l

positions (35 points). The axial positions were at the top and bottom of the block and at 1/4 block intervals.

1 l

Fig. 1.

Local point nuchering - SURVEY code analysis of FSV FTE-1 l

+

Page 11

GENERAL ATOMIC COMPANY cA-aa, I;

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TEST REFORT: NCNDESTRUCTIVE FLUf! NATION OF FSV FUEL TEST ELN'T FTI-1 Document No.

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s 8-0085 q

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.gf;.;

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Fig. 2.

FSV FTE-1, side f ace A.

f Page 12

GENERAL ATOMIC COMPANY

' GA-1484 TI M :

TEST RE?CRT: NONDESTRUCTIVE EXAMINATION OF FSV FUEL TEST ELE:ENT FTE-1 l

Document No.

I""'

906599 A

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j, y k!ci 5

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c-,...y Fig. 3. FSV FTE-1, side face 3 Page ;3

GENERAL ATOMIC COMPANY

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TEST REPORT: NCNDESTRUCTIVE EXAMINATION OF FSV FUEL TEST ELDENT F E-1 Occument No.

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906599 A

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(

l l

.w n

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4 5

52

.=

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e E

5

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Sz

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Fig. 4 FSV FTE-1, side f ace C: discentinuous vertical scratch starting near top center and extending dcwn face.

+

Page 14 j

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GENERAL ATOMIC COMPANY GA-1484 l

• M TEST REPORT: NONDESTRUCTIVE ETAMINATICN OF FSV FUEL TEST ELFL'OIT FTE-l l

Occument No.

Issue 906599 A

l i

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h. ' 4 ' i__

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3. -.92 2

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i Fig. 5.

FSV FTE-1, side face D.

Page 15 i

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EEN MNK QWMY a A-1.is, I; TEST RE? ORT: NCNDEST7.CCTIVE EXAMINATION OF FSV FUEL TEST ELEMENT FTE-1

+

Document No.

'tuus 906399 g

F

& -d i

.. =

4 1

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Fig. 6.

FT1 FTE-1, side face E.

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1 Page 16

GENERAL ATOMIC COMPANY' GA-1484 TITLE:

UST F.EPORT: NONDES3UCTIVE E GMINATION OF FSV FUEL TEST ELE!ENT FH-1 Document No.

Issue 99

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Fig. 7.

FSV FTE-1, side face F:

short vertical scratch near the upper left corner.

Page 17

GENERAL ATOMIC COMPANY g _ y,,

TEST RE70RT: NONDESTRUCTIVE E10i! NATION OF FSV FUEL TEST EL. MENT FTI-l

~

l Doc.: ment No.

906599 A

1 I

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Fig. 8.

FSV FTE-1, top surf ace.

Page 13

GENERAL ATOMIC COMPANY GA-1484 TITLE:

TEST REPCRT: NCNDESTRUCTIVE EX.O!INA!!ON OF FSV FUEI. TEST ELEMENT FTE-1 l

Cocument No.

Issus I

906599 A

i i

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I Fig. 9.

Examples of disclorations obser red on the top surf ace of FSV fuel test element FTE-1 l

l l

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Page 39 ll

GENERAL ATOMIC COMPANY GA-1484

+

' TEST REPORT: NONDES*RUC"IVE EIDf!NAT!0N OF 757 FUEL TEST EL"ENT FTE-1 Document No.

906599 A

Face E orner number Dowel Sow = -0.08 mm 5

a 3

2 1'

-0.024 -0.021

-0.021 -0.019

-0.025

? ace D

? ace F 3cw = -0.05 7

8

?

3cv = -0.05 =m

/-0.0:;3

-0.017

-0.022

-0.03S \\

15 1*

3 16

-0.

27 13

-0 035 10

/-0.035 14 -0.024 12

-0.032 5

-0.040

-0.025

/

j j

17 13 19 20 21 22

-0.035

-0.038

-0.037

-0.037 h

! -0.040 -0.046

=

27 26 i

/

-0.026 -0.039 3

50 51 52 25 24 23

=

-0.049

-0.043

-0.042 -0.039

-0.043

-0.050 5

\\

53 54 i

=

s

.E

-0.036 -0.048

.3 49 48 47 46 45 44 g

i -0.049 -0.046

-0.029

-0.040

-0.043

-0.050 l

.5 S

39 41 3

37

-0.042 40 -0.046 43

,j Face C

-0.C46 33

-0.037 42

-0.047 Face A

-0.048

-0 049 j

Sow =

3,y 0.05==

'iii 0.03 =m 34

,3 36 a

s 2

-0.042

-0.

42

-0.0 9

-0.046 i

1 23 29 30 31 32

-0.045 -0.048

-0.053 -0.052

-0.055 2

I 3cw = 0.05 mm NOTE:

Positive bow - cencave Fig. 10 Measured axial strain and Negative bev - convex bow for 757 fuel test ele =ent All strains (.11/1) in,.

..- 1 Ele =ent average axial st: sin = -0.039".

40.0097. (1c)

{

Page.

29

' G A-1484 TITLE: TEST REPORT: NCNDESTRUCTIVE EXAMATION OF FSV FUEL TEST ELEMENT FTE-1 Document No.

luus 9

99 Table 1 TIME-AVERAGED GRAPHITE IRRADIATION TEMPERATURES FOR FSV FTE-1 Temperature ('C Axial Point (a)

Local point (a 1

6 j

1 2

3 4 I 5

6 7

3 1

576 557 563 578 579 57I 571 j

2 598 578 584 600 602 595 592 y

3 619 597 603 621 622 615 612 j

4 640 616 623 641 643 636 632 E

5 663 637 645 665 667 658 655

'?

2 5

]

(a)See Figure 1, Point 1 - top of block.

5 E

5 Table 2

~

FAST NEUTRON FLUENCES FOR FSV FTE-1 5

=

2 25 2

j Fast Neutron Fluence (x10 Axial Point (a)

Local point (a{s, E>29fJHTGR) n

?

1 l

2 l3 4

5 6

7 1

.63

.73

.69

.57

.55

.62

.68 2

.63

.73

.70

.58

.55

.62

.69 3

.64

.74

.70

.58

.56

.62

.69 4

.63

.73

.70

.58

.55

.62

.69 5

.60

.70

.66

.55

.53

.59

.65 (a)See Figure 1, Point 1 - top of block

~

Page 21

-m-.

m

GENERAL ATOMIC COMPANY GA-1484 MO TEST REFORT: NONDESTRUCTIVE EXAMINATION OF FSV FUEL TEST ELEMENT FTI-1 Document No.

906599 Ime A Table 3.

DISTANCE-BETWEEN-FIDUCIAL-HOLE MEASURD'ENTS FOR FSV FUEL TEST ELi'fENT 1, Freirradia-Festirradiad Strain j

(3)

Dim 2n-tion Distance l tion Dis-

?.2/ Z

1c sion Corner (in.)

tance (in.)

~

g L

1 9.002 8.993

-0.097 0.044 L

2 9.002 8.993

-0.099 0.044 g

L 3

9.003 8.999

-0.046 0 044 i

L 4

9.004 9.000

-0.036 0.044 L

5 9.004 9.000

-0.036 0.044 g

3 L

6 9.003 8.995

-0.075 0.044 s

L BLK AV

?.003 8.997

-0.065 0.044 2

M 1

9.002 8.999

-0.025 0.044 E

M 2

9.003 8.996

-0.069 0.044 8

M 3

9.002 8.99?

-0.035 0.044 3

M 4

9 001~

8.998

-0.033 0.044 E

M S

9.003 9.000

-0.033 0.044 1

M 6

9.002 9.001

-0.004 0.044 2

M BLK AV 9.002 9.999

-0.033 0.044 j

N 1

9.001 8.998

-0.029 0.044

.E N

2 9.000 9.000 0.009 0.044 E

N 3

9.000 8.999

-0.005 0.044 j

N 4

9.000 9.002 0.021 0.044 N

5 8.999 9.000 0.016 0.044 5

N 6

9.000 9.003 0.043 0.044

.5 N

BLK AV 9.000

,9.001 0._009 0.044 E

E 1

27.005 26.991

-0.050 0.015 j

R 2

27.004 26.090

-0.053 0.015

?

R 3

27.006 26.99S

-0.029 0.015 R

4 27,005 27.001

-0.016 0.015 3

5 27.006 27.001

-0.017 0.015 R

6 27.004 27.001

-0.012 0.015 R

BLK AV 27.005 26.997

-0.030 0.015 (a) Dimension L - distance between the top 2 fiducial holes Dimension M - distance between the middle 2 fiducial holes Di=ension N - distance between the bottom 2 fiducial holes Dimension R - distance between the top and bottom fiducial holes The 4 fiducial holes were equally spaced over the elenents's length.

Page 22

GENERAL ATOMIC COMPANY

. GA-1484 TITLE: IEST REFORT: NCNDES*1UCTI7E ETXCNATION OF FSV FUEL TEST ELIMENT FTI-1 9

i Cocument No.

tuue 906599 A

l Table 4 MEASURED RADIAL STRAIN (from distance-across-flats measurements) FOR FSV FUEL TEST ELr INT FTE-1

-8 2

E bistance i

from Botten Radial Strain (AI/IM 3

of Block E'

(is.)

Face s A-D Face s B-E Face s C-F Average

.2 w

e 1.25

-0.003 0.023

-0.009 0.004 E

4.25 0.008 0.017

-0.009 0.006 7.25 0.020

-0.012 0.003

,)

10.25

-0.007 0.014

-0.006 1 13.25

-0.011 0.007

-0.022

-0.009 3

16.25.

-0.013 0.003

-0.022

-0.010 5

19.25

-0.016

-0.001

-0.022

-0.013 3

22.25

-0.027

-0.010

-0.033

-0.023

.g 25.25

-0.044

-0.015

-0.040

-0.033 3

28.25

-0.03 0

-0.025

-0.027

-0.027 l

-30.35

-0.03 4

-0.025

-0.036

-0.03 2 8

3 Block Average

-0.012 g

l

[

l l

l l

Page 23 l

l

..s

• GENERAL ATOMIC COMPANY GA-1484 TITW TEST REFORT: NONDESTRUCTIVE EXAMINA2 ION OF FSV FUEL TEST E1.EMENT FTE-1

+

l Document No.

Issue 90o..,9 A

v Table 5 COOLANT HOLE DIAMETER MEASUREMENTS FOR FSV FUEL TEST ELEMENT FTE-1 HOLE PRE-IRRADIATION POST-IRRADIATICN I RADIAL STRAIN l Diameter Diameter AI/I i ic

.(in. ) v (in.)

312 0.622 0.620

-0.359 0.186 259 0.622 0.620

-0.423 0.186 222 0.622 0.421

-0.262 0.186 191 0.498 0.497

-0.370 0.232

.g 3

219 0.622 0.621

-0.149 0.186 270 0.622 0.620

-0.310 0.136 j

319 0.622 0.600

-0.343 0.186 y

295 0.622 0.620

-0.391 0.186 2

267 0.622 0.620

-0.310 0.186 g

235 0.622 0.421

-0.181 0.186 199 0.498 0.497

-0.270 0.232 t@

216 0.622 0.620

-0.310 0.186

=

264 0.622 0.620

-0.407 0.186 E

303 0.622 0.321

-0.230 0.186 g

244 0.622 0.611

-0.262 0.186 4

213 0.425 0.624

-0.191 0.135 E

180 0.499 0.497

-0.269 0.232 j

161 0.623 0.622

-0.165 0.186 i

158 0.622 0.621

-0.214 0.136 155 0.623 0.621

-0.326 0.186 5

170 0.623 0.621

-0.310 0.186

.5 167 0.622 0.621

-0.214 0.186 E

164 0.623 0.622

-0.149 0.186 j

145 0.496 0.497 0.032 0.233 5

112 0.623 0.623

-0.005 0.196 l

S1 0.623 0.622

-0.085 0.186 22 0.623 0.623

-0.069 0.186 41 0.623 0.621

-0.326 0.186 109 0.622 0.622

-0.053 0.186 126 0.496 0.495

-0.230 0.233 90 0.623 0.623 0.043 0.184 SS 0.623 0.621

-0.279 0.196 30 0.623 0.622

-0.229 0.186 6

0.623 0.623 0.011 0.186 55 0.623 0 620

-0.406 0.186 106 0.623 0.622

-0.165 0.136 144 0.496 0.496

-0.170 0.233 103 0.626 0.625

-0.1?6 0.*SS 66 0.623 0.623

-0.005 0.186 13 0.622 0.622

-0.251 0. *. ? 6 i -0.:_a i

2 l

Page 24

..e,

LM WMY c A-148, TITLE: TEST REPORT: NONDESTRUCTIVE EXMfINATION OF FSV FUE' TEST ELDIENT FTE-1 Document No.

I"'

906599 A

Table 6 DISTANCE-BETWEEN-COOLANT-HOLE MEASUL"ENTS FOR FSV FUEL TEST ELEMENT FTE-1 PRE-IRRADIATION POST-IRRADIATION STRAIN l

]

HOLES Distance Distanca AI/I

1c

~

(in.)

(in.)

5-5 5

i 312 TO 270 1 598 1.598

-0.019 0.317 3

270 TL 219 1.598 1.599 0.062 0.317 3

219 TO 106 3.818 3.813

-0.112 0.133

,F 106 TO 55 1.597 1.597 0.034 0.312 5

55 TO 13 1.597 1.598 0.059 0.317 g

312 TO 13 12.697 12.688

-0.068 0.040 j

319 TO 295 0.659 0.465 0.954 0 770 3

295 TO 267 0.660 0.657

-0.557 0.768 267 TO 235 0.640 0.661 0.132 0.769

]

235 TO 90 4.502 4.499

-0.071 0.113

=

90 TO 58 0.459 0.659

-0 048 0.769 3

58 TO 30 0.659 0.659 0.066 0 770 3

30 TO 6

0.658 0.658 0.067 0.771 3

319 TO 6

12.193 12.185

-0.070 0.042 303 TO 264 1.598 1.599 0.028 0.317 3

264 TO 216 1.598 1.598 0.023 0 317

.5 216 TO 109 3.817 3.918 0.031 0.133 y

109 TO 61 1.598 1.597

-0.046 0.317 z

61 TO 22 1.596 1.597 0.010 0.318 303 TO 22 12.696 12.691

-0.044 0.040 170 TO 167 1 598 1.599 0.044 0.317 167 TO 164 1.598 1.598

-0.005 0.317 164 TO 161 3.818 3.826 0.224 0 133 161 TO 158 1.598 1.599 0.0S3 0.317 158 TO 155 1.596 1.5?8 0.108 0.318 170 TO 155 12.699 12.706 0.053 0.040 13 TO 22 6.037 6.038 0 015 0.034 22 TO 170 6.037 6.035

-0.025 0.084 170 TO 312 6.038 4.036

-0 039 0.034 312 TO 303 6.038 6.03S 0.009 0.0?4 303 TO 155 6.038 6.036

-0.036 0.084 155 TO 13 6.036 6.037 0.043 0.0?a 4VERAGE 6

0.00? I a.3:01 Page 25

GENERAL ATOMIC COMPANY GA-1484 TITLE: TEST REFORT: NONDESTRUCTIVE EXAMINATION OF FSV FUEL TEST ELEMENT FTE-1 Occument No*

I 8"'

906599 A

Table.7 CALCUIATED AND MEASURED STRAINS AND BOW FOR FSV FUEL TEST ELEMENT FTE-1 Time-averaged (a)

Fast Fluence (b)

Temperature (1025 n/m2 Calculated Measured

?arameeer

(*C)

E>29fJu cn )

Value Value Element average (c) 615 0.64

-0.135

-0.03920.009 axial ser ain (%)

=

j Axial strain g

distribution (%)

f Local point 1 619 0.64

-0.132

-0.038 0.009 2

597 0.74

-0.159

-0.046:0.009 h

3 603 0.70

-0.145

-0.044t0.009 2

3 4

621 0.58

-0.115

-0.025 0.009 j

5 622 0.56

-0.113

-0.027t0.009 y

6 615 0.62

-0.138

-0.04220.009 j

7 612 0.69

-0.155

-0.05020.009 h

Element average (d) 615 0.64

-0.096

-0.01210.016

-8 radial strain (%:

.e i

Radial strain (d) t distribution (%)

5 3

Top of block 573 0.63

-0.118

-0.03220.011 Middle of block 615 0.64

-0.097

-0.010!0.016 Bottem of block 659 0.61

-0.071

' O.004:0.016 Bow (mm)(*)

0.10 0.08

(* Temperature obtained from SURVEY code calculations based on the GAUGE code depletion analysis of FSV cycle 2 and the FTE-1 power history calculated by the GATT code.

The temperature uncertainty (la) is approximately 10% of l

the difference between the temperature and the gas-inlet temperature (~340*C, time averaged).

Fast neutron fluences obtained from Si!RVEY code calculations based on the CAUGE code depletion analysis of FSV cycle 2 and the axial flux prefiles Page 26

r 1

(,.,

1.-

GENERAL ATOMIC COMPANY l

GA-1484 N

TEST REPORT: NONDES3UCTTIE I:GMINATION OF FSV FUEL TEST EL.T-iT FTE-1 Occument No.

Issus l

Table 7. (Cont.)

for the FSV core, (it was assumed that FTE-1 did not significantly affect the fast neutron flux distribution). The uncertainty in the fast fluence is s

approximately 210% (le).

(c)The axial strains were obtained by subtracting the ther:a1 strain for E-451 graphite in the axial orientation at 177*C (0.062 x 10-2 =m/==)

f rom the end-of-lif e shutdown strains calculated by SURVEY / STRESS.

(d)he radial strains were obtained by subtracting the ther=al strain for E-451 graphite in the radial orientation at 177*C (0.071 x 10-2 =2/=2) from the end-of-life shutdown strains calculated by SURVEY / STRESS.

(e)The bow was calculated at the ele =ent =idplane by SURVEY / STRESS.

?,

E a

$23 5

2 3

43

'5 2

I

.3 55

.=

8 i

.e

=

1

.5 E

\\

l 2

l

=

l l

em 27 m