ML20083P555

Test Rept:Thermal Properties of Facility Fuel Element 1-2415

ML20083P555
Person / Time
Site:	Fort Saint Vrain
Issue date:	12/16/1983
From:	Price R GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
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ML20083P530	List: ML20083P527 ML20083P535 ML20083P555
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907155, NUDOCS 8404200063
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SUMMARY

TITLE TEST REPORT: THERMAL PROPERTIES OF O H&D APPROVAL LEVEL 2 FORT ST. VRAIN FUEL ELEMENT 1-2415 SDV&S O DESIGN DISCIPLINE SYSTEM 00C. TYPE PROJECT DOCUMENT NO. ISSUE N0/LTH.

N 18 RTE 7700 907155 A 4 QUALITY ASSURANCE LEVEL SAFETY CLASSIFICATION SEISMIC CATEGORY ELECTRICAL CLASSIFICATION I SC-1 CAT-I N/A

,,p APPROVAL ISSUE PREPARED ISSUE DATE DESCRIPTION /

FUNDING APPLICABLE ENGINEERING QA PROJECT PROJECT CWBS NO.

A DEC 1 8 g R. Price G. En e D. Initial Release BrusY W.J.%ca. u/3c,43 66 $ w/o 7736.902.130 I P Gray 19

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l CONTIN'JE ON GA FORM 14851 NEXT INDENTURED DOCUMENTS

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NON-CONTROLLED COPY VERIFY ISSUE STATUS WITH DOCUMENT CONTROL 8404200063 840433 PDR ADOCK 05000267 FRIOR TO USE P PDR REV SH REV l

SH 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 48 49 50 46 l 47 51 52 53- 54 55 56 REV l

SH 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 20 22 23 18 l 19 21 24 25 26 27 28 i PAGE 1 0F 20 i _ _____________ .-

~ . . . .. . - - .- .. . - . . . _ - _ _ _ __. _

GA-1484 (REV.10/82) .

, TITLE:

TEST REPORT: THERMAL PROPERTIES OF FORT ST. VRAIN FUEL ELEMENT 1-2415 Document No.

907155 I""' A s

TABLE OF CONTENTS Page

1. IN TRODU CTI O N --------------------------------------- 4

2. MAT E R IAL --------------------------------------------- 4 2.1 Unit radiated H-3 27 G raphite--------------------- 4 2.2 Ir ra di a t e d Ma t e r i al----------------------------- 4 R

E 3. TES T ME TH ODS ----------------------------------------- 5 5

= 3.1 Thermal Expansivity------------------------------ 5 I 3.2 Th e rm al Dif f us iv i ty----------------------------- 6 3.3 Calibrations------------------------------------- 6 5

.g 4. RES U L TS --------------------------------------------- 7

.5 4.1 Th e rm al E xpa ns ivi ty----------------------------- 7 m

! 5 4.1.1 Unirradiated Specimens------------------- 7 j 4.1.2 Irradiated Specimens--------------------- 7 C

g 4.2 Th e rm al Co n du c tiv i ty---------------------------- 3 3ed

.e 4.2.1 Unir radiated S pe cimens------------------ 8 E 4.2.2 Irradiated Specimens--------------- ----

8

.s y 5. SU MMARY AND CON CLUS IONS------------------------------ 9

=m j 6. RE F ERE N C ES ------------------------------------------- 10 Page 2

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TEST REPORT: THERMAL PROPERTIES OF FORT ST. VRAIN FUEL ELEMENT 1-2415 Document No. 907155 isme g LIST OF TABLES

1. Thermal Expansivity of Unirradiated H-327 Graphite, Billet 6484-136, 25-500*C- ------------------------- 11

2. Thermal Expansivity (25-500*C) of Coupon Specimens from Fort St. Vrain Element 1-2415 (H-327 Graphite)-- 12

3. Thermal Conductivity of Unirradiated H-327 Graphite, Billet 6484-136, Radial Direction, Edge of Billet---- 13

4. Thermal Conductivity of Coupon Specimens from Fort St.

! g Vrain Fuel Element Direction)---- 1-2415 (H-327 Gra

- -------------------phite; Radial o ----------------- 14

.c I

E, is LIST OF FIGURES fi

1. Sectioning of FSV Fuel Element 1-2415- ------------- 15 i g' 2(a). Coring Plan - Faces A, B, and Cs t e d s pe cimen s y sh a ded ) -------------------------(Te -------------------

.E 16 g 2(b). Coring Plan - Faces D, E, and F (T s t e d s pe cim en s

.g o

sh a de d ) --------------------------e ----------------- 17 j 3. Thermal Expansivity of Graphite from Fuel Element

,s 1-2415 f or Each Face of the Block-------------------- 18 3 4. Thermal Conductivities of Graphite from Fuel Element -

z l-2415 as a Function of Measurement Temperature------- 19

5. Thermal Conductivity of Graphite from Fuel Element 1-2415 f or Each Face of the Block-------------------- 20 i

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TEST REPORT: THERMAL PROPERTIES OF FORT ST. VRAIN FUEL ELEMENT 1-2415 Document No.

1.

907155 '"" A INTRODUCTION The test plan for the destructive examination of the cracked Fort St. Vrain fuel element 1-2415 calls for measurements of mechanical and thermal properties on coupon specimens cored f rom the element af ter removal of the f uel [1]. The results of the tensile tests are reported in Ref. [2]. This report gives the results of thermal expansivity and thermal diffusivity measure-ments. Thermal diffusivity values are converted to thermal con-ductivity by multiplying by the densicy and the heat capacity.

j Check-out tests on unirradiated H-327 graphite are also reported.

E E

o 2. MATERIAL i

f y 2.1 Unitradiated H-327 Graphite d

)m Unirradiated comparison specimens were machined from H-327 a graphite billet 6484-136, Great Lakes Carbon Corp. lot number 56, f piece number 5612.

Specimens were taken about 1-in. from the edge j of a 6-in. deep slab cut perpendicular to the billet axis at about

-j the midlength location. The thermal expansivity specimens were j rods measuring 1.0-in. long x 0.25-in. diameter. Those with even

.c identification numbers were oriented parallel to the billet axis,

.E z and those with odd identification numbers were oriented transverse j to the billet axis. The thermal diffusivity specimens were discs measuring 0.40-in, diameter x 0.08-in. thick, with the thickness dimension oriented radially with respect to the billet axis.

2.2 Irradiated Material Specimens of irradiated graphite were taken from the cracked Fort St. Vrain fuel element 1-2415, made from H-327 graphite, which had received a neutron exposure of approximately 1.55 x 1021 n/cm (E < 0.18 MeV, HTGR) at a time- and volume-averaged temperature of approximately 650*C [1] . After removal of

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TEST REPORT: THERMAL PROPERTIES OF FORT ST. VRAIN FUEL ELEMENT 1-2415 Document No.

907155 ime g the fuel the element was cut into sections as shown in Figure 1, and the 6-in. deep section was used for machining coupon specimens for mechanical and thermal property tests. The six hexagonal faces were identified by letter, as shown in Figure 1. The cracked face was designated B.

A slab approximately 0.44-in. thick was cut adjacent to

.g each of the six f aces and cores were taken as shown in Figure 2.

E The small diameter cores measured approximately 0.27-in. diameter j x 4-in. long, and the large diameter cores measured approximately j 0.40-in. diameter x 0.44-in. long. The test specimens were ma-g, chined f rom the cores with a lathe enclosed in a glove box. The j final dimensions for the thermal expansivity specimens were 0.25 y, in. diameter x 1.00 in. long, and those f'or the thermal diffusi-f vity specimens were 0.40 in. diameter x 0.08 in, thick. Thermal

.}Q expansivity specimens with both axial and transverse orientations y were tested. All the thermal diffusivity specimens were oriented j with the heat flow direction radial with respect to the fuel ele-

] ment axis. The specimens were identified by the f ace number fol-lowed by the core number as shown in Figure 2.

E

.e

!! 3. TEST METHODS 3.1 Thermal Expansivity Thermal expansivity measurements were made in a fused silica dilatometer with an argon atmosphere. The dilatometer enclosure was exhausted through an absolute filter. The tempera-ture was raised from room temperature to 500-600*C at 3*C/ minute.

The thermal expansivity was calculated from the dilatation at 500*C. Further details are given in Ref. [31. Three replicate i

specimens for each location and orientation were tested.

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TEST REPORT: THERMAL PROPERTIES OF FORT ST. VRAIN FUEL ELEMENT 1-2415 Document No. 907155 l** A 3.2 Thermal Diffusivity The thermal diffusivity was measured by subjecting the front face of the specimen to a pulse of radiant energy from a xenon flash tube while the temperature of the back face was moni-tored with a chromel-alumel thermocouple. The enclosure was ex-hausted through an absolute filter. The thermal diffusivity,a 2

4 (cm /s), is related to the specimen thickness, I (cm) and the time e for the back f ace to rise to half its maximum value, t1/2(s) by j the expression:

I

.=

y, eg2 F. O "

5 t 1/2 e

j where e is a constant which is equal to 0.139 when heat losses are j small and t 1/2 is long compared with the pulse length [ 41. The j thermal conductivity, K(cal /cm-s *C) , was calculated from a using j the expression:

E

.c 5 K= ap C p

.s I 3 j where p is the density in g/cm and C p is the specific heat. Val-3 ues for Cp were obtained from the literature [5]. Tests were made at intervals between room temperature and 600*C, using an argon atmosphere. Two or three replicate specimens from each location were tested; one was measured at intervals of 100*C (110*C), and the others were measured at intervals of 200*C (110*C). Further details of the test method are given in Ref. [4] .

3.3 Calibrations The dilatometer calibration was checked using a specimen of NBS-certified tungsten. The measured thermal expansivity agreed with the certified value to within 1%. The rise-time measurement

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TEST REPORT: THERMAL PROPERTIES OF FORT ST. VRAIN FUEL ELEMENT 1-2415 Document No. I"'

907155 A for the thermal diffusivity determination is measured with a quartz crystal oscillator which is periodically checked against the line frequency and is accurate to better than 0.01%. Poco AXM-50 graphite is used as a reference material for check-out purposes. Measurements on this material agreed with the accepted values obtained by other laboratories [6] to within 5%.

4 4. RESULTS E

4.1 Thermal Expansivity a

I y, 4.1.1 Unirradiated Specimens E

5 i j The thermal expansivity measurements on unirradiated H-327 3 graphite (25-50 0

• C) are listed in Table 1. The mean values were j 1.23 x 10-6 .C-1 for the axial direction and 2.69 x 10-6 .C-1 for i the transverse direction. These compare with nominal hand book

~0 ~1

$ values of 1.20 x 10 *C (axial) and 3.07 x 10 -6 *C'1 (trans-8

.y verse) [7] . The agreement is satisfactory.

.5 5 4.1.2 Irradiated soecimenn 5

z l The thermal expansivity measurements on the irradiated specimens are listed in Table 2. The same data are plotted for each f ace of the fuel element in Figure 3. The test data have very little experimental scatter and there is no systematic varia-tion in thermal expansivity between the six f aces of the fuel ele-ment. The mean values are 1.38 x 10 -6 *C ~1 (axial) and 3.28 x 10-6 .C-1 (transverse).

For the irradiation conditions experienced by the fuel ele-ment, the thermal expansivity would be expected to increased by 2%

over the unirradiated value [7]. The expected values are 1.23 x

, 10-6 *C'1 (axial) and 3.14 x 10-6 .C-1 (transverse), which are in good agreement with the measured values.

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TEST REPORT: THERMAL PROPERTIES OF FORT ST. VRAIN FUEL ELEMENT 1-2415 Document No. 8 907155 .

A 4.2 Thermal Conductivity 4.2.1 Unirradiated snec4= ann The test data on unirradiated material are listed in Table 3, and plotted as a function of measurement temperature in Figure

.g 4. The data show considerable specimen-to-specimen scatter. This f is probably due to the coarse filler grain size of H-327 graphite;

.5 the largest grains are approximately the same size as the specimen j thickness. Since the thermocouple wires make point contacts on 5, the back of the specimen, the measured thermal diffusivity is sen-f sitive to the local grain orientation at the thermocouple con-E tacts.

i 2

j Handbook values [7] for the thermal conductivity of unirra-i diated H-327 graphite (radial orientation) are shown by the upper j solid line in Figure 4. Within the scatter of the data, the agreement with the measured values is satisfactory.

.s

.j 4.2.2 Irradiated Sneci=ana E

Table 4 shows the thermal diffusivity measurements on the irradiated specimens. The data are plotted for each f ace of the fuel element in Figure 5, and the average values are shown as a function of measurement temperature in Figure 4. The data scatter is similar to that of the unirradiated specimens.

Neutron irradiation reduces the thermal conductivity of graphite and flattens its dependence on measurement temperature.

For a fluence of 1.55 x 10 21 n/cm 2 at 650*C, current design

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TEST REPORT: THERMAL PROPERTIES OF FORT ST. VRAIN FUEL ELEMENT 1-2415 Document No. 907155 issue A methods [7] predict that at room temperature the thermal conducti-vity of H-327 graphite in the radial direction would be reduced f rom 127 w/m-K, to 31 w/m-K, and at 600*C the conductivity would l be reduced f rom 80 w/m-K to 32 w/m-K. The predicted values are shown by the lower solid line in Figure 4. Agreement with the average of the measurements at each temperature is good.  ;

.g The data in Figure 5 do not reveal any obvious systematic E trend in thermal Conductivity with the f ace of the fuel element, j and an analysis of variance on the data showed no significant j j face-to-face variations. Any variations that might have been g, present (caused, for example, by differences in the irradiation j temperature of the f aces) , would be masked by the scatter in the e data.

N s

,@ 5.

SUMMARY

AND CONCLUSIONS N

As part of the destructive examination of Fort St. Vrain j fuel element 1-2415, thermal expansivity and thermal diffusivity f

j measurements were made on coupons machined from each of the six hexagonal faces of the graphite block.

~

Thermal conductivity g

values were calculated from the thermal diffusivities. There were no significant variations in either thermal expansivity or thermal i conductivity between specimens f rom the six faces, and the mea-l surements agreed well with current design values for E-327 graph-ite. The thermal expansivity measurements were very reproducible, but the thermal conductivities showed considerable scatter. ?ny variations in thermal conductivity between the six f aces due to differences in irradiation temperature would have been masked by scatter in the data. It is concluded that there was nothing abnormal about the thermal properties in the vicinity of the crack in face B, and the properties of the fuel element are consistent 1 with the general population of H-327 graphite billets.

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TEST REPORT: THERMAL PROPERTIES OF FORT ST. VRAIN FUEL ELEMENT l-2415 Document No. isme 907155 A i l

6. REFERENCES

[1] F. McCord, " Test Procedure for the Destructive Examination of Fort St. Vrain Fuel Element 1-2415," Document No. 906770, Issue A (Feb. 25,1983) .

[2] R.J. Price, " Tensile Properties of Fort St. Vrain Fuel Element 1-2415," Document No. 907057, Issue A (Sept. 23, 1983).

j [3] " Standard Method of Test for Linear Thermal Expansion of E Rigid Solids with a Vitreous Silica Dilatometer," ASTM Test 5 Method E-228 (ASTM Annual Book of Standards, 17, ASTM, S Philadelphia, 1982).

[4] " Standard Method of Test for Thermal Diffusivity of Carbon

) and Graphite by a Thermal Pulse Method," ASTM Test Method 2" C-714 (Annual Book of ASTM Standards,15, ASTM, Philadelphia, 1983).

s I [5] A.T.D. Butland and R.J. Maddison, "The Specific Heat of 5 Graphite: An Evaluation of Measurements," J. Nucl. Mater. 49,

.s 45 (1973-74).

@ [6] R.E. Taylor and H. Groot, "Thermophysical Properties of Poco j Graphite," High Temperatures-High Pressures, 12, 147 (1980).

$ [7] Graphite Design Data Manual, Document No. 906374, Issue 1

.s (May 19, 1983).

E 3

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TEST REPORT: THERMAL PROPERTIES OF FORT ST. VRAIN FUEL ELEMENT 1-2415 Document No. 907155 Ime 3 Table 1. Thermal Expansivity of Unirradiated H-327 Graphite, Billet 6484-136, 25-500*C

~

Orientation Specimen Number CTE (10 * *C-1)

E Axial 2C 1.37

.5 4C 1.04, 1.10

[R 6C 1.20, 1.42 h Mean (i std. dev.) 1.23 1 0.17 5

e Transverse 1C 2.69, 2.77 N 3C 2.87, 2.86 5 5C 2.31, 2.63 i

i Mean (i std. dev.) 2.69 i 0.21

.!2 6

.E E

.e 5

z l

l 1

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TEST REPORT: THERMAL PROPERTIES OF FORT ST. VRAIN FUEL ELEMENT 1-2415 Document No. I"'

907155 A Table 2. Thermal Expansivity (25-500*C) of Coupon Specimens f rom Fort St. Vrain Fuel Element 1-2415 (B-327 Graphite)

Axial Transverse  !

Specimen Specimen -

Face Number CTE (10-0 *C-1) Number CTE (10-6 .C )

A 2 1.44 1 3.37

$ 4 1.29 7 3.29 E 6 1.30 9 3.26 t Mean 1.34 i 0.08 Mean 3.31 i 0.06

?.

t B 2 1.39 1 3.28

$ 4 1.30 3 3.25

.g 6 1.30 7' 3.24

$ Mean 1.33 1 0.05 Mean 3.26 1 0.02 a

5 C 2 1.35 1 3.43 5 4 1.40 3 3.25

-l- 6 1.45, 1.31 5' 3.27 E

$ Mean 1.38 1 0.06 Mean- 3.32 i 0.10

.e E D 2 1.52

.5 3 3.39 4 1.40 5 3.19 y 6 1.44 7" 3.33 i

j Mean 1.45 1 0.06 Mean- 3.24 i 0.08 E 2 1.42 1 3.29 4 1.34 3 3.36 6 1.42 5' 3.21 Mean 1.39 1 0.05 Mean 3.29 i 0.08 F 2 1.34 1 3.25 4 1.45 5' 3.22 6 1.34 7~- 3.36 Mean 1.38 1 0.06 Mean ~ 3.28 i 0.07 All Faces 1.38 i 0.07 3.28 i 0.07 Handbook

+ Value 1.23 1 0.40 3.14 1 0.70 Page y l l

GA Techn'slogies inc, GA-1484 (REV.10/82)

+ TITLE:

TEST REPORT: THERMAL PROPERTIES OF FORT ST. VRAIN FUEL ELEMENT 1-2415 Document No. 907155 Ima A Table 3. Thermal Conductivity of Unirradiated H-327 Graphite, Billet 6484-136, Radial Direction, Edge of Billet Specimen Thermal Conductivity (w/m-K) a t (*

j Number 25'C 100*C 200*C 300*C 400*C 500*C E

= TD-11 77.3 99.3 71.6 I

TD-13 125.3 115.2 107.3 103.3 90.3 90.3 E

.g TD-15 135.1 104.1 80.7

$ Mean 112.5 115.2 103.5 103.3 80.8 90.3 a

s a

's

,E (a' Actual measurement temperature was within 10*C of the e nominal temperature.

E b

.s j ..

z l

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Page 13 l

Not:tions in this column indicate where changes have been mide

-! S Qd k l

Table 4. Thermal Conductivity of Coupon Specimens from Fort St. Vrain Fuel Element m" T l 1-2415 (H-327 Graphite; Radial Direction) Si

$ 0 Specimes Thermal Conductivity (w/m-K) at g h F;ce Number 25aC 100er 200*C 300*C 400*C 500*C 600*C g e

A TD-13 40.9 42.8 40.7 39.8 42.3 40.6 35.8 D3 TD-15 41.4 45.8 40.0 33.1 N ta 5 TD-11 38.3 41.5 40.9 40.5 38.2 38.9 40.6 TD-13 44.9 55.0 44.4 38.1 ks TD-15 40.9 43.8 38.3 36.3 $ @

N >

C TD-11 33.9 38.5 35.3 35.9 22 TD-13 28.1 28.8 28.8 30.0 28.2 27.7 32.4 d TD-15 40.8 44.8 40.9 34.5 g E 7 D TD-11 35.6 48.2 46.3 37.9 39.2  ! O h TD-13 TD-15 28.5 29.5 32.7 24.3 35.4 32.0 22.2 30.7 27.9 25.6 26.9 B, y y z g to E TD-11 29.7 30.4 29.7 26.7 A

m 5

ga TD-15 30.5 34.1 34.0 33.6 34.0 33.0 36.1 e

. lll3 F TD-13 31.9 37.4 37.4 31.6 $ < 9 TD-15 20.2 23.5 24.6 23.7 22.5 22.9 20.1 g m

f z

All Mean 34.3f6.7 33.9 7.4 38.18 8 35.117.6 3 4.916.7 31.816.9 32.815.7 m C

Handbook 30.7 31.9 32.9 33.1 32.7 32.4 31.8 @

7 -

N i  ! =

E g > e

" H n

w

GA Techn logies inc, GA-1484 (REV.10/82)

.y TITLE:

TEST REPORT: THERMAL PROPERTIES OF FORT ST. VRAIN FUEL ELEMENT 1-2415 Document No. 907155 issue A s.ad,,f Ju h

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i Page 15 1

GA Techn51ogies inc, GA-1484 (REV.10/82)

+ TITLE:

TEST REPORT: THERMAL PROPERTIES OF FORT ST. VRAIN FUEL ELEMENT 1-2415 Document No. 907155 issue A g ~ mn- - -  :

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GA TechnIlogies inc, GA-1484 (REV.10/82)

TITLE:

TEST REPORT: THERMAL PROPERTIES OF FORT ST. VRAIN FUEL ELEMENT l-2415 Document No. 907155 issue A

1. s 6 4.'2.

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FACE F Coring Plan - Faces D, E, and F (Tested specimens shaded)

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GA Technnlogies inc, GA-1484 (R EV.10/82)

+ TITLE:

TEST REPORT: THERMAL PROPERTIES OF FORT ST. VRAIN FUEL ELEMENT 1-2415 Document No.

907155 A

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l Figure 3. Thermal Expansivity of Graphite From Fuel Element 1-2415 for Each Face of the Block Page 18

GA Technologias Inc.

GA-1484 MEV.10/82) i , TITLE:

l TEST REPORT: THERMAL PROPERTIES OF FORT ST. VRAIN FUEL ELEMENT l-2415 ,

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Figure 4. Thermal Conductivities of Graphite from Fuel Element 1-2415 as a Function ~of Measurement Temperature

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GA-1484 (R EV.10/82)

+ TITLE:

TEST REPORT: THERMAL PROPERTIES OF FORT ST. VRAIN FUEL ELEMENT 1-2415 l Document No. 907155 issue A 1

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Figure 5. Thermal Conductivity of Graphite from Fuel Element 1-2415 for Each Face of the Block Page 20